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NEA/NSC/DOC/(95)03/IV Volume IV LEU-COMP-THERM-074 MIRTE PROGRAM FOUR 4.738-WT.%-ENRICHED URANIUM-DIOXIDE FUEL-ROD ARRAYS IN WATER SEPARATED BY A CROSS-SHAPED SCREEN OF TITANIUM (5 MM AND 10 MM THICK) Evaluator Nicolas Leclaire Institut de Radioprotection et de Sûreté Nucléaire, IRSN Internal Reviewers Isabelle Duhamel François-Xavier Le Dauphin Institut de Radioprotection et de Sûreté Nucléaire, IRSN Independent Reviewer John D. Bess Idaho National Laboratory
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Page 1: MIRTE PROGRAM FOUR 4.738-WT.%-ENRICHED URANIUM …€¦ · NEA/NSC/DOC/(95)03/IV Volume IV LEU-COMP-THERM-074 Revision: 0 Page 3 of 196 Date: September 30, 2011 The 43 experiments,

NEA/NSC/DOC/(95)03/IV Volume IV

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MIRTE PROGRAM FOUR 4.738-WT.%-ENRICHED URANIUM-DIOXIDE FUEL-ROD

ARRAYS IN WATER SEPARATED BY A CROSS-SHAPED SCREEN OF TITANIUM (5 MM AND 10 MM THICK)

Evaluator

Nicolas Leclaire Institut de Radioprotection et de Sûreté Nucléaire, IRSN

Internal Reviewers

Isabelle Duhamel François-Xavier Le Dauphin

Institut de Radioprotection et de Sûreté Nucléaire, IRSN

Independent Reviewer

John D. Bess Idaho National Laboratory

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MIRTE PROGRAM FOUR 4.738-WT.%-ENRICHED URANIUM-DIOXIDE FUEL-ROD ARRAYS IN WATER

SEPARATED BY A CROSS-SHAPED SCREEN OF TITANIUM (5 MM AND 10 MM THICK)

IDENTIFICATION NUMBER: LEU-COMP-THERM-074 SPECTRA KEYWORDS: Acceptable, Apparatus B, critical approach, interacting configurations, light water, low

enriched, MIRTE, reflector, screen, structural materials, thermal, titanium, UO2 rod arrays

1.0 DETAILED DESCRIPTION

1.1 Overview of Experiments

The MIRTE (Matériaux Interaction Réflexion Toutes Epaisseurs)a program (Reference 1) has been carried out from December 2008 to June 2010 at the CEA (Commissariat à l’Energie Atomique et aux Energies Alternatives) Valduc Center on the Apparatus B assembly (see Figure 1). The purpose of the MIRTE program was to measure integral reactivity characteristics of various structural materials that are typically used in nuclear facilities. The intended use of the data is to validate computer codes and associated nuclear cross section data that are used for criticality safety and reactor physics applications.

Figure 1: View of the Apparatus B facility.

a The English translation is Materials, Interaction, Reflection, all Thicknesses.

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Phase 1 of the MIRTE program consisted of 43 sub-critical approaches extrapolated to critical conditions using the neutron amplification method. Three types of experimental setups have been built (see Figure 2):

(1) Interacting configurations with large screens, which consisted of two arrays separated either by water or screens with a thickness varying from 5 cm to 30 cm composed of iron, nickel, zirconium, aluminum, lead, copper, concrete with varying water contents (3%, 6%, 9%), or an empty aluminum box,

(2) Interacting configurations with thin plates, involving four arrays separated by water or cruciform plates with a thickness lower than 2 cm composed of copper, nickel, iron, titanium.

(3) Reflected configurations, which consist of one array, reflected on all four lateral sides by water, aluminum or borated glass walls.

1 2

3

Figure 2: Schematic view of the experimental device.

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The 43 experiments, which involved 4.738 wt.% enriched UO2 rod arrays, included 19 experiments with tested screens, nine reference experiments in which the screens were replaced by water or an aluminum box filled with air, and 15 reproducibility experiments with or without material. Only eight experiments (comprised of four repeatability or reproducibility experiments—three with titanium and one with only water) are documented in this report. Repeatability experiments were appropriately combined into a total of four experiments (two with titanium and two reference experiments). These four experiments were evaluated and determined to represent acceptable benchmark experiments. In order to easily identify the different experiments, they were named according to the number of arrays involved in the configurations (4A for titanium experiments), the material to be tested, and its thickness (in millimeters). A reference experiment was identified by adding an “R” at the beginning of the experiment identifier and, concerning reproducibility experiments, the kind of reproducibility was added at the end of the identifier as follows:

(1) Rv for repeatability experiments, which consisted of a new sub-critical approach after water draining without any change in the configuration. This kind of experiment will give information about the uncertainties on the water height measurement and the extrapolation method.

(2) Rb(S1) for reproducibility experiments S1 type, which consisted of a new sub-critical approach after water draining and removal of the experimental device (support pedestal and lattices) from the experimental tank without any change in the configuration, allowing the estimation of the uncertainty on the rods positioning due to the gap between grid holes and rods.

(3) Rb(S2) for reproducibility experiments S2 type, which consisted of a new sub-critical approach after water draining, removal of the experimental device, moving and repositioning of lattices baskets, which highlights the uncertainty in lattice positioning.

(4) Rb(S3) for reproducibility experiments S3 type, which consisted of a new sub-critical approach after water draining, removal of the experimental device (support pedestal and lattices), moving and repositioning of lattices baskets and use of a new rods sample (rods sample chosen among 1261 rods). The uncertainty in rod sampling is assessed.

(5) Rb(S4) for reproducibility experiments S4 type, which consisted of a new sub-critical approach after a complete dismantling of the configuration, to evaluate the uncertainty in the screen positioning.

Table 1 presents the five titanium experiments (plus three reference cases without titanium) with four arrays of UO2 rods. A number of the critical assemblies performed in the Apparatus B facility at Valduc have been evaluated as ICSBEP benchmark experiments.

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Table 1: Experimental data for thin titanium screen experiments.

Experiment Experiment

Number

Array Geometry (nx × ny)

Last reached Sub-critical Height (cm)

Average Critical Height (cm)(b)

± 2σσσσ 4A-Ti-005 3034 10 × 10 68.739 70.063 ± 0.045

4A-Ti-005-Rv 3035 10 × 10 68.637 70.048 ± 0.039

4A-Ti-005-Rb(S2) 3036 10 × 10 68.642 70.094 ± 0.054

4A-Ti-005-Rb(S4) 3037 10 × 10 68.413 69.742(a) ± 0.055

R4A-Eau(c)-005 3044 9 × 8 58.502 59.982 ± 0.082

R4A-Eau-005-Rb(S2) 3045 9 × 8 58.497 60.010 ± 0.084

4A-Ti-010 3049 11 × 10 87.979 89.483 ± 0.028

R4A-Eau-010 3050 9 × 8 58.192 59.793 ± 0.091 (a) This height is not included within the uncertainty margins of the 4A-Ti-005 reference critical

height, which may be due to rod sampling and screen positioning effects. (b) This height is the average of the critical heights given by at least four of the six neutron

detectors. (c) “Eau” means “water” in French.

1.2 Description of the Experimental Configuration

The experimental configuration of Apparatus B was composed of four arrays of UO2 fuel rods held by a basket, which were placed on a pedestal inside a right parallelepiped (or rectangular) tank. The tank was located on the floor in the middle (approximately) of a large room. Water, which was used as moderator and reflector, was introduced incrementally from the bottom of the tank.

All configurations involved arrays with a 1.6-cm square lattice pitch.

Titanium experiments differed from each other by the screen thickness, by the number of rods per array, and therefore by the water level.

1.2.1 Critical Approach and Results

The experiments were based on the subcritical approach technique, with critical conditions estimated using extrapolation. The subcritical approach parameter was the water level. Two Am-Be neutron sources were used to drive the approach. Neutron counting rates were measured with six BF3 counters, which provided a “C” counting rate (depending on the array height, H, that was immersed in water) and consequently the variation of the corresponding keff of the assembly. At the end of the approach, all neutron counters were completely immersed in water. The water height was measured by a limnimeter (conductivity probe). The function 1/C = f(H) was extended by linear extrapolation to determine the critical height from water height measurements, as explained in Figure 3. In general, the level was raised very close to the critical one, such that the final keff was approximately within -β/10 ≈ -65 × 10-5 from criticality. It should be noted that the critical water height given in Table 1 corresponds to the average critical water heights obtained using measurements from at least four neutron counters.

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11-GA50002-51

C = C /(1-k )0 eff

When H HC 1/C 0

H0

1/C effK = F(H)

H

HC

Water heightmeasurement,

Rod array

UO2 rod

Fissile zone upper limit level

Pedestal

Water input and output

Neutron counters

Counting rate, C

Fissile zone lower limit level

Limnimeter

Figure 3: Principle of the experiments (screen not modeled).

The critical water height is derived from the limnimeter measurement of water height, and the extrapolation to the criticality (inverse of the counting rate to zero). Consequently the uncertainty on critical water heights is evaluated through the uncertainty which results from the limnimeter measurement and the uncertainty on the average critical height.

As the tolerance of limnimeters giving the water height is very low (less than 1/100 mm), the uncertainty on the average critical height can be assimilated into the uncertainty of the extrapolation to zero of the inverse count rate (methods uncertainty).

The uncertainty on the extrapolated critical heights reported in Table 1 is given with a level of confidence of 95.45% (2σ).

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Five experiments with two cruciform thin titanium screens were performed. The characteristics (water height, array size) of titanium experiments are given in Table 1. Array geometry parameters nx and ny (number of lateral rods) are sketched in Figure 4.

ny

nx

UO rods2

Titanium screen

Water

Figure 4: Description sketch of 4A-Ti-005 and 4A-Ti-010 configurations.

1.2.2 Room

The Apparatus B tank was approximately centered in a concrete cell named C172, in the radiological control zone, on the ground floor of Building 10 in the Valduc Nuclear Center.

The cell was 12.1 m long, 8.8 m wide and 10.0 m high, with 1.45-m-thick concrete walls. The thickness of the concrete floor was 0.40 m. The thickness of the ceiling varied from 0.70 m (at the edges) to 1.10 m (in the middle). The concrete was covered with a decontaminable paint.

1.2.3 Experimental Tank

The experimental tank had internal dimensions of 189.7 cm × 189.7 cm horizontally and 140 cm vertically. It comprised 0.4-cm-thick walls and a 0.6-cm-thick bottom and was manufactured from stainless steel Z2CN18-10. The walls and bottom were reinforced with U-shaped girders. The tank was equipped with a limnimeter (needle of measurement) that followed the free upper level of water and provided the water height. The zero-level measurement of the limnimeter was the bottom of the fissile column. The limnimeter precision was ±0.01 mm. Because the arrays were centered in the tank, more than 20 cm of water surrounded the lateral sides of the fuel rod arrays.

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1.2.4 Support Structure

The support pedestal (stainless steel Z2CN18-10), which enabled the experimental devices to be installed in the tank, was located at the bottom of the experimental tank (Figure 5). It was composed of the following parts:

• A support plate 186 cm × 186 cm, 2.5 cm thick, which was reinforced with L-shaped girders; this plate was pierced with eight holes to allow the water rise (see Figure 8).

• Four legs. • A tubular structure situated at the four pedestal corners, 9 cm in outer diameter and 0.549 cm thick.

These tubes were soldered to horizontal tubes, which had the same sections (the tubular structure is visible in Figure 5).

The upper face of the pedestal was 30.25 cm above the bottom of the pool tank. The support plate was equipped with rails which allowed positioning the baskets precisely in the middle of the pedestal.

Figure 5: Pictures of the support structure with L-shaped reinforcements.

1.2.5 Setup Device

The titanium experiments used the interacting configuration with the thin screens device (see Configuration 2 in Figure 2).

It should be noted that the setup device slightly differed for reference configurations without screens: the setup device for configurations with screens is kept, and additional metallic parts were introduced to guarantee the water gap between the rod arrays. In particular, lower and upper wedges were positioned in contact between the grids of the two rod arrays. Their plans are provided in APPENDIX I. A cross-shaped titanium screen was placed between the four lattices of UO2 rods. Figure 6 shows the experimental device, which comprised four movable aluminum baskets. The square grids were pierced by 15 × 15 holes. A dedicated aluminum device was manufactured to maintain the screens’

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positioning all along the height. A distance of half a pitch (0.8 cm) was imposed between the center of the outermost rods of the four arrays and the cruciform screens.

Figure 6: Experimental device for titanium experiments without titanium screens.

The four movable baskets (Figure 7) were made of the following parts (see Table 2): • A bottom plate of the basket which could be approximately divided into a rectangular part and a

triangular part. It was placed just below the array to support the fuel rods. • Two grids vertically separated by 97.9 cm (center to center) with the following dimensions:

24 cm long, 24 cm wide, 0.4 cm thick, and 0.98 cm for diameter of holes. • L-shaped angle brackets shown in Figure 8 (0.2 cm thick, 2.5 cm wide and 100.7 cm high) that

joined the end plate and the two grids. • An aluminum frame composed of four legs (four vertical tubes) linked together by horizontal tubes

that maintained the grids. The basket plans are given in APPENDIX H.

Screen Frame

Movable Baskets

Leg of the Screen Frame

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Figure 7: Lateral view of the movable baskets.

Legs of the Movable Basket

Bottom Plate Small Horizontal Tube

Large Horizontal Tube

Lower Grid

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Table 2: Characteristics of the movable basket parts.

Structure Element of structure

Rectangular tube wall thickness

(cm)

Width (cm)

Height (cm)

Length (cm)

Legs (vertical tubes) 0.4 5 97.15 5

Large horizontal tube 0.4 5 5 23.5 Support

Small horizontal tube 0.4 5 5 15

Grids 24 0.4 24

Rectangular part 33.5 1.2 34 Bottom plate

Triangular part With two sides equal to 24 cm and the last one equal to

34 cm

Figure 8: Upper view of the grids with their L-shaped angle brackets during assembling of the configuration (the support plate holes that allow the water to rise are visible).

It can be noted that the bottom of the fissile column was at the same level as the upper side of the bottom grid; the distance between the top of the basket bottom plate and the top of the lower grid was 1.8 cm. Axial position of the fissile column was checked visually. The screens were positioned on four vertical AG3 aluminum alloy plates that were 24 cm long, 1.2 cm thick, and 6.7 cm high. Figure 9 presents views of the frame that maintained the titanium screens. The frame dimensions are given in Table 3.

L-shaped Angle Brackets

Aluminum Screen Frame

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Figure 9: Description of the screen frame.

Vertical Screen Guides

Upper Grid of the Basket

Horizontal Tubes

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Table 3: Characteristics of the screen frame parts.

Structure Element of structure Rectangular tube

wall thickness (cm)

Width (cm)

Height (cm)

Length (cm)

4 legs (vertical tubes) 0.4 5 112.1 5

4 horizontal tubes 0.4 5 5 50 Screen frame Vertical guides

maintaining the screen 10.25 for 4A-Ti-005

10 for 4A-Ti-010 4 95.4

1.2.6 Fuel rods

In experiments performed at the Valduc Apparatus B facility before 1994, the fuel was clad with AGS. These rods were reclad in 1995 with Zircaloy-4 claddings. Measurements were performed on 100 rods (at the top, middle, and bottom of each rod) to determine the outer diameter of the clad. The average value and its associated standard deviation is: 0.949245 ± 0.000439 (1σ) cm. The outer clad diameter was measured with a micrometer (palmer) whose precision was ± 0.0005 cm. Measurements were also performed on fissile column height, fissile column weight, fissile pellet diameter, spring mass, and plug mass. Table 4 gives the measured values and the associated standard deviation (1σ) for the main parameters. The clad inner diameter is known only by the fabrication specification. Complete measurement of masses and dimensions are recorded for many of the 1261 fuel rods. However, the placement of a given rod in the assembly was not recorded. Measurement data for the fuel rods available at Valduc for use in these experiments are tabulated in APPENDIX J. The UO2 fuel rods used for the experiments (Figure 10) contained uranium oxide fuel, enriched to 4.738 wt.% 235U. The fuel column was made of sintered oxide pellets, each 1.4954 ± 0.0068 cm long and 0.78919 ± 0.00176 cm in diameter (measurement values, from References 2 and 4). The pellet diameter was measured with a palmer (micrometer), whose precision was ± 0.005 cm. The total rod length, including end plugs and retaining spring, was 102.082 ± 0.04 cm (measurement value).

Table 4: Fuel rods characteristics (References 2 and 4).

Parameter Mean Value Standard Deviation (1σ)

Number of Measurements

Pellet Diameter (cm) from measurement statistics

0.78919(a) 0.00176(a) 53

Pellet Height (cm) 1.4954 0.0068 53

Inner Clad Diameter (cm) 0.836(b) 0.00289(b) 0

Outer Clad Diameter (cm) from measurement statistics

0.9492(c) 0.000439(c) 300

Fissile Column Height (cm) 89.765 0.254 1261

Fissile Column Mass (g) 455.78 2.82 1261

Rod Height (cm) 102.082 0.04 1261 (a) The diameter of 53 pellets has been measured using a micrometer (palmer); the uncertainty in the

measured value does not include the accuracy of micrometer, which is 0.005 cm.

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(b) Conversion to 1σ of the manufacturing tolerance dividing by 3 (c) The diameter of 300 claddings has been measured using a micrometer (palmer); the uncertainty in the

measured value does not include the accuracy of micrometer, which is 0.0005 cm.

Figure 10: Fuel rod (mean dimensions).

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The average height value of the fissile column was 89.765 ± 0.254 (1σ) cm, which is in agreement with the original specification value of 90 cm ± 1 cm. The average density and average oxide mass are given in Section 1.3. Plugs of rod ends are also made of Zircaloy-4. Both plugs have a cylindrical form with a truncated end simplifying the attachment. Their characteristics are given in Table 5.

Table 5: Characteristics of end plugs (Reference 4).

Height (cm) Diameter (cm) Mass (g)

Value Tolerance Value Tolerance Value Uncertainty (σσσσ)

Number of Measurements

Upper Plug 1.468 0.024 0.95 0.005 3.4675 0.0047 15 UO2 Rods Lower Plug 1.8 0.005 0.95 0.005 4.6321 0.0138 10

Above the fuel, between the end of the fissile zone and the bottom of the top end plug, a stainless steel spring retains and compresses oxide pellets inside the clad, ensuring contact between them. The spring had the following characteristics:

• Material: Stainless steel Z10CN18-09 • Length:a 9.049 cm • Diameter: 0.78919 ± 0.00176 cm (measurements) • Number of spirals: 30 • Spring wire diameter: 0.1445 ± 0.0025 cm (manufacturing tolerance) • Mass: 8.09583 ± 0.00895 g (measurements).

Rods were arranged in arrays at a 1.6-cm square pitch. They were carefully placed and experimenters visually checked their alignment in the two horizontal, perpendicular directions. It was also checked that the rods were perfectly straight. The rods were installed into the grid, and observed outside the tank. It was seen that the arrays were aligned in such a way that light should pass through the rows. There were no visible rod deviations.

Four sources of uncertainty associated with rod positioning were considered:

(1) The hole position uncertainty due to error in adjustment of the hole-piercing device. For the grids employed in the experiments, no measurements of the pitch have been performed for these grids. From manufacturing tolerances in Reference 1 (0.01 cm), the 1σ uncertainty is then obtained dividing the

manufacturing tolerance by 3 giving 0.006 cm.

(2) The rod positioning uncertainties due to the space between the rod’s clad and the hole are the following: ± 0.030755 cm for the hole diameter 0.98 cm (0.98-0.949245 = 0.030755). This uncertainty is assumed to be random. It follows an equiprobable distribution; therefore, 1σ = 0.0307/√3 = 0.0177.

(3) The grid hole diameters were not measured. However, the tolerance on the hole diameter is reported to be 0.01 cm on the grids sketch. The uncertainty on the hole diameter is then obtained dividing the

tolerance by 3 giving then 0.006 cm.

a Compressed length in the final produced rods.

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(4) The rod outer clad diameter uncertainty is measured to be ± 0.000439 cm (1σ); the systematic uncertainty (± 0.0005 cm) given by the palmer is used.

1.2.7 Titanium screens

The titanium screens were cruciform plates made of two thin metallic plates grooved in their middle on a height of 500 mm. They were then assembled as a cruciform device to be installed between the four UO2 arrays (see Figures 11 and 12). The design of the screens was optimized to ensure their positioning and minimize the experimental uncertainties. For that purpose, much effort was devoted to 3D measurements of the tested screens (Figures 13, 14, and 15) using different techniques. The dimensions, perpendicularity, and flatness of the different screens were investigated. A micrometer (palmer device) was used to measure the thickness of the screen (Figure 15) as well as the dimensions of the groove. The thicknesses were measured in the mesh shown in Figure 16. Measured dimensions of the screens from the analysis reports are given in Table 6. The reported values are provided in APPENDIX G. The screens’ dimensions were also measured (see Figures 13 and 14) using a laser tracker at different positions of a mesh similar to that shown in Figure 16. The laser tracker measures the thickness, the length, and the height with a precision of 0.015 mm. The given thicknesses’ values and uncertainties are the means and the standards deviations of all the measurements. The given uncertainties for lengths and heights are the systematic uncertainties (see Table 6). The values given in Table 6 were obtained as follows:

• Only one series of thickness measurements were made for the two screens (2 measurements) used in experiment 4A-Ti-005 and those measurements were made using a micrometer. Laser tracker measurements were not possible for screens that are so thin. Values for height and width were obtained using the laser tracker.

• Two series of thickness measurements were made for the two screens (4 measurements) used in 4A-Ti-010. Those measurement were made with both the laser tracker and more traditional methods such as a micrometer (especially for the groove). Values for height and width were obtained using the laser tracker.

During their assembly (see Figure 11), the titanium screens are slipped into guidance rails. The tolerance interval on the slit in which the screens are introduced is [+0.1 mm; +0.5 mm]. Moreover, the assembling of the two screens by means of the groove requires a perfect perpendicularity of the two assembled screens.

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Figure 11: Picture of the 5-mm titanium plates during the assembling of the configuration.

Figure 12: Picture of the 5-mm titanium plates assembled for the experiment.

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Figure 13: Thin screen during measurement with laser tracker.

Face 3

Face 6

Face 2 Face 4

X

Y

Screen

X

Z

X

ZLaserball

Diameter 6

11 - G A5 0 0 0 2 - 6 6

Figure 14: Thin screen during measurement with laser tracker.

Diameter

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Figure 15: Thin screen during measurement with micrometer device.

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Figure 16: Mesh for the metallic screen measurement.

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Table 6: Measured dimensions of the titanium screens.

Material Configurations

Thickness (cm)

± mean standard deviation

Height (cm) ± precision (Laser tracker)

Length (cm) ± precision (Laser tracker)

0.5023 ± 0.0009(a) 100.0114 ± 0.0015 36.5117 ± 0.0015 4A-Ti-005

0.5026 ± 0.0006(a) 99.9939 ± 0.0015 36.5063 ± 0.0015

1.0033 ± 0.0010(a)

1.0018 ± 0.0010(b) 100.0035 ± 0.0015 40.2027 ± 0.0015

1.0031 ± 0.0009(a)

Titanium

4A-Ti-010

1.0033 ± 0.0010(b) 100.0053 ± 0.0015 40.2027 ± 0.0015

(a) Measurements with palmer device (precision of the palmer: 0.005 mm). (b) Measurements with laser tracker device (precision of the laser tracker: 0.015 mm).

1.2.8 Neutron Counters and Sources Support

Six BF3 neutron counters were arranged around the core. Four of them were placed facing the four sides of the core at a distance of 6 cm laterally from the core boundary and 20 to 38 cm above the basket bottom. The two others were placed facing the sides of the core at a distance of 10 cm from the core boundary and 20 cm above the basket bottom.

The neutron counters were located behind the rods array at a distance from the rods array boundary given in APPENDIX E. The two Am-Be neutron sources (3.57.109 Bq) were located on two middle fuel rods, 25 cm above the bottom plate.

1.2.9 Command and control room

The command and control room was adjacent to the experiment cell. Experimenters carried out the subcritical approach electronically and remotely, according to the information provided by the control panel, microcomputers, and video cameras. 1.3 Description of Material Data

The UO2 fuel rod comprised uranium oxide pellets clad with Zircaloy-4. Titanium screens were placed between arrays of the fuel rods with AG3 aluminum alloy and stainless steel Z2CN18-10 materials providing structural support for the entire assembly, which was reflected and moderated by light water at room temperature.

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1.3.1 Isotopic Content of Uranium

The uranium of the UO2 fuel was enriched to 4.738 wt.% 235U. The results of recent isotopic analyses on two pellet samples (1998) are provided in References 2 and 4 and are reported in Table 7. The uranium isotopic content was measured by thermal ionization mass spectrometry (TIMS), which gives very accurate results.

Table 7: Results of TI/MS measurements in 1998 (2σ uncertainties).(a)

Isotope(b) at.% (Sample 1) at.% (Sample 2) 234U 0.0308 ± 0.001 0.0306 ± 0.001 235U 4.7956 ± 0.004 4.7949 ± 0.004 236U 0.1375 ± 0.001 0.1371 ± 0.001 238U 95.0361 ± 0.020 95.0374 ± 0.020

(a) Measured by FBFC (Franco-Belge de Fabrication de Combustible). (b) 238U atomic percentage is [100-(234U at.%+235U at.%+236U at.%)].

1.3.2 Stoichiometry of Uranium Oxide

Two values of the O/U stoichiometry derived from References 3 and 4 are reported in Table 8.

Table 8: Results of stoichiometry analysis for the UO2 fuel.

Reference Experimental Study Relative to UO2 Rods

(Reference 4)

FBFC Analysis Certificate (Reference 3)

Date 1980 1998 O/U 2.0035 2.000 ± 0.001 (1σ)

1.3.3 Density of Uranium Oxide

Measurements were performed on 1261 rods during the production of new claddings by FBFC/Pierrelatte in 1995. The average values are the following:

• Average oxide weight: 455.78 ± 2.82 g (1σ) • Average fissile height: 89.765 ± 0.254 cm (1σ) • Average linear density: 5.0778 ± 0.0282 g/cm (1σ, the average linear density was obtained by

averaging the linear densities of each rod.).

Later, in 2000, the diameter of 53 oxide pellets was measured. The average diameter was 0.78919 ± 0.00176 cm (1σ) (see Reference 4). In References 2 and 4, it is stated that the nominal density is equal to 10.38 ± 0.04 (3σ) g/cm3.

1.3.4 Uranium Oxide Impurities

The impurity content is reported in References 2 and 4. It was provided by FBFC (Franco-Belge de Fabrication de Combustible) measurements in 2000. Three elements were reported to be over the detection

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limit: aluminum, iron, and silicon. Other elements (referred to as undetected impurities) were under the detection limit. These data are reported in Table 9.

Table 9: Uranium oxide impurity report provided by FBFC.

Element Al Fe Si B Ca Cd Cr Mg Mo Ni Ti ppm(a) 18 85 101 <0.35 <20 <0.53 <15 <6 <20 <20 <10

Element Th Zn C Cl F N Dy Eu Gd Sm ppm(a) <2 <10 <4 <5 <2 <7.5 <0.05 <0.05 <0.1 <0.15

(a) Parts per million by weight relative to UO2; i.e., [(weight of element)/(weight of UO2) × 106] .

1.3.5 Zircaloy-4 Characteristics

Plugs and clad were made of Zircaloy-4. Its composition was provided by the European manufacturer of zirconium, CEZUS. Three Zircaloy-4 analysis certificates were provided in the report on UO2 rods

(References 2 and 4) concerning, respectively, the cladding tubes, bottom end plugs, and top end plugs. The differences in the contents of the cladding and bottom and top plugs of element were within one standard

deviation of measurement precision. The composition given in Table 10 corresponds to the cladding analysis.

Table 10: Selected Zircaloy-4 analysis for UO2 fuel-rod cladding tubes, chemical composition.

Element Zr(a) N O Sn Fe Cr Weight % 98.12347 0.0031 0.1368 1.366 0.222 0.118 Element C Si Al Hf H

Weight % 0.01286 0.0099 0.00194 0.00556 0.00037 (a) The zirconium weight mass (%) is determined by difference.

The density value of Zircaloy-4 (specification value) given in the references was ρ = 6.55 g/cm3. The basic report also gives the contents of Zircaloy-4 impurities. Values were provided by the manufacturer

for samples from three positions in the alloy ingot.a Detected impurities were included in the chemical composition (

Table 10). Other impurities are reported in Table 11.

Table 11: Detection limits for the undetected impurities in fuel-rod zircaloy-4 cladding.

Element B Ca Cd Cl Co Cu Mg Mn Mo ppm(a) <0.4 <10 <0.4 <10 <10 <10 <10 <10 <10

Element Nb Ni Pb Ta Ti U V W ppm(a) <50 <40 <20 <100 <10 <0.5 <20 <30

(a) Parts per million by weight relative to Zircaloy-4; i.e., (weight of element)/[(weight of Zircaloy-4) × 106]

a The melted metal is transformed into an ingot, which is used to produce the Zircaloy-4 bars used to produce the cladding. Compositions are measured in three positions: on top, in the middle and at the bottom of the ingot.

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1.3.6 Spring Stainless Steel

The spring was made of stainless steel Z10CN18-09. Its composition as reported in the analysis certificate in Reference 4 is given in Table 12.

Table 12: Z10CN18-09 stainless steel chemical composition (ρ = 7.9 g/cm3).

Element N Fe(a) Cr C Si Cu Weight % 0.046 70.3674 18.51 0.08 0.7 0.36 Element Mn Ni P S Mo Co

Weight % 0.92 8.79 0.02 0.0026 0.15 0.054 (a) The iron weight mass (%) is determined by difference.

1.3.7 Moderator and Reflecting Water

Several chemical analyses of the water stored in tanks, which was used for the core reflection and moderation, were carried out after specific experiments in the frame of the MIRTE program. Results of the test measurement made before the experiment, which is consistent with all the other measurements, are reported in Table 13.

Table 13: Impurities in water.

Element Concentration

(mg/l) Element Concentration

(mg/l) Element Concentration

(mg/l) Element Concentration

(mg/l)

Cl 10.1 S 3.1 Fe < 0.001 Sn < 0.010 Na 4.4 K 0.38 Ni < 0.001 Gd < 0.001 Mg 1.7 Ca 98.3 Cu 0.028 Pb < 0.010 Al < 0.001 Ti < 0.001 Zr < 0.001 W < 0.001 Si 2 Cr 0.001 Nb < 0.001 Sr 0.064 P < 0.01 Mn < 0.001 Mo < 0.001

1.3.8 Titanium Screens

During the fabrication process, the chemical analyses of most elements were performed in the U.S. by Evans Analytical Group (EAG). A 2 × 2 × 20-mm pin was sectioned from each titanium sample, cleaned with HF and HNO3 acid, and rinsed with deionized water and ethanol. Elements were individually scanned by a glow discharge ion source while the samples were sputtered. The glow discharge mass spectrometry (GDMS) system is well characterized with a Ta Quality Control sample and has an accuracy and precision of about 20 to 30%. Titanium reference material (TIM 573) was analyzed and used to correct measured data for B, Al, Si, P, S, V, Cr, Mn, Fe, Ni, Cu, Mo, and Sn.a

The results of these analyses are reported in Table 14 and in Table 15. A complete description of the GDMS technique is given in APPENDIX F. a EAG Quantitate Analysis of Impurities for Idaho National Laboratory, Job# S08Q9239 for Titanium samples (A47A-C1 10-mm, A55C/C2 5-mm), December 9, 2008.

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Table 14: Results of chemical analysis of both titanium screens performed in 2008 – detected elements.

ppm/weight Elements Titanium 5 mm Titanium 10 mm

Fe 1200 1400 Cr 240 240 Ti Balance Balance Sn 18 34 B 0.09 0.16 Hf 0.37 0.23 In 0.13 0.23 Sb 1.9 1.4 C 160 130 N 20 17 O 0.19 wt% 0.16 wt%

Mg 0.08 0.04 Al 15 51 Si 110 130 P 9.3 19 S 11 9.5 Cl 1 0.28 V 0.98 1.2

Mn 28 50 Co 1.7 1.8 Ni 110 100 Cu 13 12 Ga 0.19 0.26 Ge 0.17 0.19 As 3.1 5.1 Zr 8.1 5.6 Nb 34 23 Mo 2.2 2.8 Ru 0.05 0.04 W 0.28 0.31 Pb 0.07 0.13 Th 0.002 0.003 U 0.004 0.009

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Table 15: Results of chemical analysis of titanium screens performed in 2008 – elements reported to be under the detection limit.

Elements ppm/weight Elements ppm/weight Li <0.01 Cs <0.01 Cd <0.1 Ba <0.01 Be <0.005 La <0.005 Bi <0.05 Ce <0.005 F <0.5 Pr <0.005

Na <0.01 Nd <0.005 K <0.05 Sm <0.005 Ca <5 Eu <0.005 Sc <0.1 Gd <0.005 Zn <0.1 Tb <0.005 Se <0.05 Dy <0.005 Br <0.1 Ho <0.005 Rb <5 Er <0.005 Sr <3000 Tm <0.005 Y <200 Yb <0.005

Rh <0.1 Lu <0.005 Pd <0.05 Ta <16 Ag <0.1 Re <0.01 Te <0.05 Os <0.01 I <0.01 Ir <0.01 Pt <0.05 Au <0.1 Hg <0.1 Tl <0.01

At the end of 2010, new chemical analyses were performed by FILAB (France) using ICP-AES technique. The results are reported in Table 16 and in Table 17 for the 4A-Ti-005 and 4A-Ti-010, respectively.

In addition, the material densities were measured using helium pycnometry. The 5-mm titanium screen density was evaluated to be 4.491 ± 0.002 g/cm3. The 10-mm titanium screen density was evaluated to be 4.5049 ± 0.0005 g/cm3.

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Table 16: New chemical analysis of titanium screen (5 mm thick) performed in December 2010, ρ = 4.491 ± 0.002 g/cm3.

Table 17: New chemical analysis of titanium screen (10 mm thick) performed in December 2010, ρ = 4.5049 ± 0.0005 g/cm3.

Elements Fe Cr Ti B Li Cd Eu

Weight % 0.1 0.018 Balance <0.005 <0.005 <0.005 <0.005

Measurement Method

ICP AES ICP AES ICP AES ICP AES ICP AES ICP AES ICP AES

Element Gd Hf In Ir V Sn Zr

Weight % <0.005 <0.005 <0.005 <0.005 <0.005 <0.005 <0.005

Measurement Method

ICP AES ICP AES ICP AES ICP AES ICP AES ICP AES ICP-AES

Element Mo Dy

Weight % <0.005 <0.005

Measurement Method

ICP AES ICP AES

Elements Fe Cr Ti B Li Cd Eu

Weight % 0.13 0.018 Balance <0.005 <0.005 <0.005 <0.005

Measurement Method

ICP AES ICP AES ICP AES ICP AES ICP AES ICP AES ICP AES

Element Gd Hf In Ir V Sn Zr

Weight % <0.005 <0.005 <0.005 <0.005 <0.005 0.007 <0.005

Measurement Method

ICP AES ICP AES ICP AES ICP AES ICP AES ICP AES ICP-AES

Element Mo Dy

Weight % <0.005 <0.005

Measurement Method

ICP AES ICP AES

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1.3.9 Characteristics of Other Structural Materials

Compositions of other materials are given in Table 18 (Reference 2). The given values for AG3 aluminum alloy and stainless steel Z2CN18-10 correspond to specification values. It should also be noted that concrete walls were covered with a thin layer of paint, known as “washable and decontaminable,” with an unknown composition.

Table 18: Compositions of other materials.

Material Density (g/cm

3)

Nuclides Weight (%)

Si ≤0.4 Fe ≤0.4 Cu ≤0.1 Mn ≤0.5 Mg 2.6-3.6 Cr ≤0.3 Zn ≤0.2 Ti ≤0.15

AG3 Aluminum Alloy(a) (basket, grids, and plates)

2.67

Al Balance C <0.03 Cr 18 ± 1 Ni 10 ± 1 Fe Balance Mn ≤ 2 Si ≤ 1 S ≤ 0.03

Stainless Steel(a) (support pedestal and experimental tank)

Z2CN18-10

7.9

P ≤ 0.04

Material Density (g/cm

3)

Nuclides Atom densities (atom/barn-cm)

Concrete (cell hall)

2.4013(c)

H 10B O Al Si Ca Fe

1.035 × 10-2 1.602 × 10-6 4.347 × 10-2 1.563 × 10-3 1.417 × 10-2 6.424 × 10-3 7.621 × 10-4

Air (b) Not

mentioned N O

4.1985 × 10-5 1.1263 × 10-5

(a) Data comes from the AFNOR French standard. (b) A simplified air composition, calculated from the Handbook of Chemistry and Physics, 87th

edition, 2006-2007. (c) Calculated from atoms/barn-cm data. 10B content is an equivalent content, providing a neutron

absorption equal to that of the total impurities in a thermal flux.

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1.4 Temperature

Experiments were carried out at temperatures ranging from 18.6°C to 19.8°C. These temperatures were obtained by thermocouples in the room where the experiment was performed (Cell 172) and in the reflector. They are reported in Table 19. The diameter of these thermocouples was 3 mm, their length 550 mm and 1150 mm. The maximum error of the thermocouple temperature measurement was ±0.2°C. Information on calibration of thermocouples is not available. The thermocouples were located next to the tank walls, at a height of 968 mm and 368 mm from the bottom of the experimental tank and more than 200 mm from the arrays of rods.

Table 19: Temperatures during and after the experiments.

During the experiments At the end of the experiments

Experiment Number Configuration

Room (Cell 172) temperature

(°C)

Reflector temperature

(°C)

Room (Cell 172) temperature

(°C)

Reflector temperature

(°C) 3034 4A-Ti-005 20.6 19.4 20.9 19.5

3035 4A-Ti-005-Rv 20.6 19.8 19.7 19.7

3036 4A-Ti-005-Rb(S2) 18.1 19.1 18.6 19.0

3037 4A-Ti-005-Rb(S4) 18.7 18.6 19.1 18.8

3049 4A-Ti-010 18.0 18.8 18.0 18.6

3044 R4A-Eau-005 19.4 20.0 19.4 19.9

3045 R4A-Eau-005-Rb(S2) 19.1 19.8 19.2 19.7

3050 R4A-Eau-010 18.0 18.6 18.1 18.5

1.5 Supplemental Experimental Measurements

No additional measurements were performed.

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2.0 EVALUATION OF EXPERIMENTAL DATA

Eight experiments are documented in this report, including four reproducabilty experiments (three with 5-mm-thick titanium sheets and one reference case) that were appropriately combined into four experiments. Those four experiments were evaluated and determined to represent acceptable benchmark experiments. In 1995, in the framework of the renovation of Apparatus B, measurements and chemical analyses were performed on the new fuel rods, which were reclad (1995 to 2000). The pellet surplus was used for chemical analysis in Valduc and in the FBFC (Franco-Belge de Fabrication de Combustible) control laboratory in Romans (France).

The MIRTE program used the same rods that were analyzed between 1995 and 2000.

Furthermore, it can be noted that, for the MIRTE program, a dedicated effort was made to reduce the experimental uncertainties. Thus, measurements of the screens dimensions with laser trackers were performed, as well as chemical analyses for the screens composition. This came in addition to the stringent specification values. 2.1 Statistical Approach

The impact on reactivity of different uncertainties is evaluated through a statistical approach. Depending on the available data (measurements or fabrication tolerance), two different methodologies are used.

2.1.1 Evaluating the Uncertainty on Measurements

The uncertainty on a measured value is the quadratic sum of the experimental standard deviation (measurement dispersion) and the measurement accuracy (measurement device calibration). Concerning the UO2 rods, it should be noted that not all the rods used in the experiments were measured during their recladding process. The uncertainty attributed to the rods should be divided into three components:

• The uncertainty of the measurement sample

• The sampling of rods used for the experiment (the rods used for the experiment were randomly chosen from the 1261 inventory)

• The sampling of measured rods (around 100).

Based on Formula 11 in Section C.12 of APPENDIX C of the ICSBEP Uncertainty Guide, it was shown by calculation that the sampling uncertainty associated with the rods involved in the experiment is negligible. As a consequence, the sampling uncertainty does not need to be considered.

Moreover, given that the number of measured values is almost sufficient to determine that the distribution is close to normal, it was decided to attribute the uncertainty of the measured population to the entire population of rods.

2.1.2 Evaluating the Uncertainty on Manufacturing Tolerances

In the case of manufacturing tolerances, the available data are a nominal value and bounds. A uniform law should be applied to model this tolerance (division by 2√3 to scale the bounds to one standard deviation).

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2.1.3 Propagation of the Uncertainties in Terms of ∆∆∆∆keff

Uncertainty in the Measurement Concerning the UO2 rods and more specifically their positioning, caution should be used when propagating the uncertainties in terms of ∆keff. In fact, the approach of applying the standard deviation to the perturbed calculation and then dividing the obtained ∆keff by the square root of n (number of rods in the array) to account for independent random variation of the parameter (according to its Gaussian distribution) could overestimate the result. As a consequence, whereas most parameters uncertainties are treated as systematic, the rod positioning uncertainty uses the square root of n factor.

Calculations The uncertainties were propagated to ∆keff by performing either one APOLLO2-MORET 4 Monte Carlo calculation (CRISTAL V1 package using the JEF2.2 library) using the Correlated Sampling method (also named A2M4 CS or MORET 4 perturbation) or two multi-group APOLLO2-MORET 4 Direct Calculations (also named A2M4 DC using the JEF2.2 library). In the first case, the keff variation is given without Monte Carlo uncertainty (a negligible uncertainty is obtained due to the method); in the second case, the keff variation must take into account the associated Monte Carlo statistical standard deviation. When using a Monte Carlo code to calculate keff of a perturbed case, the formula considered is:

( )[ ]2

2

2

4

1ixix

N i

i

ikk

x

uk δδδ −+ −××

=∆ ∑ .

where (k+δxi- k-δxi) represents the change in keff induced by change +δxi - -δxi on parameter pi, ui is the standard uncertainty of the parameter ρI, and N is the number of different parameters whose effects are included. In all Monte Carlo calculations run with a standard deviation of less than 0.0001, a ∆keff of less than 0.0001 is considered as being negligible. Summaries of uncertainties and their reactivity effects are presented at the end of Section 2 in Table 35 and in Table 36. In addition, a comparison was made for propagated uncertainties between APOLLO2-MORET 4 (correlated sampling method), APOLLO2-MORET 4 (two direct calculations) and continuous energy MORET 5 (two direct calculations) with a low Monte Carlo standard deviation (=0.0001) for direct calculations. A general good agreement between calculations from the two codes was obtained. The results are reported in APPENDIX D. 2.2 Material Data and Chemical Uncertainties

The propagation in terms of ∆keff of all material and chemical uncertainties is summarized in Table 35 and Table 36.

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2.2.1 Isotopic Content of Uranium in UO2 Rods

Different reports provide the results of measurements performed over a period of 20 years (1978 to 1998). The latest measurement results are provided by FBFC (Franco-Belge de Fabrication de Combustible) and reported in Table 7. The retained isotopic composition, which is the mean of the two samples, is given in Table 20.

In order to evaluate the reactivity effect of this uncertainty, MORET 4 perturbation calculations were performed.

Table 20: Retained isotopic composition (1σ uncertainties).

Element at.% wt.% 234U 0.03070 ± 0.0005 0.03020 ± 0.0005 235U 4.79525 ± 0.002 4.73760 ± 0.002 236U 0.13730 ± 0.0005 0.13620 ± 0.0005 238U 95.03675 ± 0.02 95.0959 ± 0.02

The uranium 1σ uncertainties of the isotopic composition from Table 20 are assumed to be representative of the rod population encountered in the experiments. As can be seen, the uncertainty of 238U is higher than the sum of uncertainties of other isotopes. Anyway, a variation of ±0.02% of 238U isotopics, keeping other isotopes constant (including 235U), is calculated to be negligible. The other isotopics are kept constant because their uncertainties are too low to counterbalance the 238U uncertainty.

Similarly, 234U and 236U isotopics are varied separately by ±0.0005. As the uranium vector needs to be normalized to keep the total amount of uranium constant, 235U is decreased or increased by the same variation. The uncertainties are also calculated to be negligible. 235U isotopics is varied by its uncertainty range of ±0.004. 234U and 236U isotopics remain constant. The total amount of uranium is kept constant by decreasing or increasing 238U (see Table 36).

Table 21: Perturbation calculation parameters: 4A-Ti-005 and 4A-Ti-010.

Element at.% 234U 0.03070 235U 4.79525 +/- 0.004 236U 0.13730 238U 95.03675 -/+ 0.004

The ∆keff results should be divided by 0.004/0.002 to scale to 1σ.

2.2.2 Stoichiometry

The retained value for the O/U stoichiometry is the 1998 measurement by FBFC, i.e., 2.000 ± 0.001 (1σ).

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The value of 2.0035 was calculated on the basis of a 235U enrichment of UO2 fuel rods slightly differing from the 4.738 wt.%; this value was found in old experimental reports. In fact, this value was reevaluated and consequently, the O/U was reviewed at the same time. The impact on reactivity worth of a ±0.01 variation is calculated using the perturbation method and is found to be negligible (<0.00001).

2.2.3 Oxide Density and Pellet Diameter

Data regarding the measured masses and dimensions of fuel rods available for use in these experiments are given in APPENDIX J. However, the experimental procedure did not require that identification of the exact rod placement with the assemblies be recorded, and the measurements of fuel rod parameters is not 100% comprehensive for all 1261 fuel rods. Only smaller subsets of fuel rods were characterized with detail for some measurements. Therefore, the method described below was utilized to assess uncertainty in fuel rod dimensions and mass, and is considered to represent a bounding estimate.

2.2.3.1 Pellet diameter The 1σ uncertainty associated with the pellet diameter was assessed while keeping the fuel linear density constant. As a consequence, the density needed to be corrected accordingly. The following formula was applied:

12

∆+=∆

RR

R

ρρ

where )()(,2

RRRRLength

mass ρρρπ

ρ −∆+=∆××

= .

The uncertainty of the measured pellet diameter is measured to be 0.00176 cm (1σ). However, the precision of the measuring device (palmer) being ±0.005 cm, this systematic uncertainty is calculated to be predominant. A MORET 4 perturbation calculation is performed for ±0.01 cm variation of the pellet diameter. The corresponding density variation is ± 0.26 g/cm3. This result is then scaled to 1σ (systematic uncertainty: 0.005 cm) by dividing by four.

2.2.3.2 Oxide Density In References 1, 2, and 4, it is stated that the density is equal to 10.38 ± 0.04 (3σ) g/cm3. This value was calculated using the 2010 Handbook a propagation uncertainty formula (APPENDIX B) on the basis of linear density and diameter uncertainties. A correlation between these two uncertainties was considered. In a new approach, the uranium oxide density uncertainty has been calculated considering that the linear density and diameter uncertainties are uncorrelated. It should be noted that the uncertainty is, in fact, the density dispersion obtained on 1261 rods. It includes the pellet heterogeneity and diameter dispersion of the fissile column, which varies from one rod to another.

a NEA/NSC/DOC(95)03 – International Handbook of Evaluated Criticality Safety Benchmark Evaluation Experiments – September 2010 Edition

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Actually, the model considers the same density (10.38 g/cm3) for all rods. This simplification is responsible for an uncertainty, which comprises two components:

• The uncertainty of the rod population (random), which is found to be ±0.073 g/cm3 (1σ)

• A sampling uncertainty because only N rods were randomly drawn from a population of N0 = 1261 available rods.

Random component

The average linear density has been obtained by measurements of mass and height of fissile columns made on 1261 rods during their fabrication process leading to 5.0778 ± 0.0282 g/cm (1σ).

It has been checked that the distribution of measurements was close to Gaussian.

It was seen in Section 2.2.3.1 that the pellet diameter was measured and that the associated uncertainty was ±0.00176 cm (1σ).

The random component (see APPENDIX B) of the density uncertainty was derived from the linear density uncertainty and was calculated to be ±0.073 g/cm3.

A MORET 4 perturbation calculation, using the correlated sampling method, is performed to propagate the 1σ uncertainty in terms of ∆keff. A density variation of +0.073 g/cm3 and –0.073 g/cm3 was applied.The impact on reactivity worth of the variation on density is reported in Table 35 and in Table 36. The random component of the uncertainty is calculated to be negligible.

Systematic component

The systematic uncertainty of mass measurement is estimated to be ±0.5 g (mass reported without decimal places). The corresponding 1σ uncertainty is ±0.289 g since an equiprobable distribution is assumed.

Similarly, the systematic uncertainty of critical height measurement is estimated to be ±0.001 cm (height reported with three decimal places). The corresponding 1σ uncertainty is ± 0.00058 cm since an equiprobable distribution is assumed.

Moreover, the systematic component of the pellet diameter uncertainty is ±0.005 cm. The corresponding 1σ uncertainty is ±0.00289 cm since an equiprobable distribution is assumed.

These systematic uncertainties are propagated using formulas (1), (2), and (3) in order to obtain the density uncertainty:

2

2

2

2

2

2

HdmdensityHdm

σρσρσρσ ×

∂∂+×

∂∂+×

∂∂= , (1)

Hd

m

××=

4

2πρ , (2)

Hdm ××

=∂∂

4

12π

ρ,

Hdd ××−=

∂∂

4

23π

ρ,

2

2

4

1

HdH ××−=

∂∂

πρ

, (3)

with m being the mass of the fissile column, H, the height of the fissile column, and d the diameter of the fissile column.

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m = 455.78 g, H = 89.765 cm, d = 0.789 cm

This density uncertainty is assessed to be 0.076 g/cm3.

To propagate the 1σ uncertainty in terms of ∆keff, the density of pellets was varied by 0.076 g/cm3, keeping their diameter constant. One APOLLO2-MORET 4 calculation using the correlated sampling method was performed with the reference density and the perturbed one in the APOLLO2 calculation.

All the results are reported in Table 35 and in Table 36.

2.2.4 Oxide Impurities

The fuel also contains impurities. In 2000, impurity analyses were performed on available pellets; the results are provided in Table 9. Except for three impurities of specifically measured content (Al = 18 ppm, Fe = 85 ppm, and Si = 101 ppm, ppm being the ratio of impurity weight to oxide weight in units of 10-6), the given values correspond to the measurement limit of the apparatus. The impurity content (except aluminum, iron, and silicium) taken at the limit of detection include absorbing elements as boron, cadmium and gadolinium. The uncertainty on oxide impurities composition is assumed to be 100% of elements detection limits.

The effect on keff of the impurities below the detection limit is evaluated through a sensitivity calculation with MORET 4 perturbation module based on the correlated sampling method. The calculation is made with all the undetected impurities at their detection limit (100%). This uncertainty is considered to be a bounding Type-B uncertainty. The impact on reactivity worth of the undetected impurities is 0.00042 for 4A-Ti-005 and for 4A-Ti-010.

This value is then divided by 3 to scale to 1σ. The impact on reactivity worth of the detected impurities (Al, Fe, and Si) was also studied. Two APOLLO2-MORET 4 direct Monte Carlo calculations with and without these three elements were performed.

2.2.5 Zircaloy-4 Density

It is assumed that the last digit of the density value is significant. Thus, the corresponding uncertainty is ±0.005 g/cm3 , i.e. σ = 0.0029 g/cm3, if the uniform-probability hypothesis is assumed.

The effect of this uncertainty has been calculated with MORET 4 (using the correlated sampling method) on 4A-Ti-005 and 4A-Ti-010. A density variation of ±0.05 g/cm3 is applied in the calculation. The obtained ∆keff is then scaled to 1σ.

2.2.6 Spring

As the neutronic influence of the springs is quite low, no perturbation calculations have been made concerning the composition and dimensional uncertainties.

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2.2.7 Water Impurities

The effect of water impurities has been assessed for 4A-Ti-005 experiment by the difference between a model using water without impurities and a model where the impurities are explicitly modeled (see Table 13). The calculated reactivity effect is lower than 0.00001 for all experiments. Consequently, water impurities were not considered further.

2.2.8 AG3 Aluminum Alloy Density

The maximum contents of silicon, iron, copper, manganese, chromium, zinc, and titanium are retained. The magnesium content corresponds to the middle of the interval. Aluminum is calculated as the balance. No uncertainty value is provided for AG3 aluminum alloy density in the experimental reports. As a consequence, one-half of the last digit is retained (0.005 g/cm3) as an uncertainty. The corresponding 1σ uncertainty is equal to 0.00229 g/cm3. The effect on keff is calculated to be negligible.

2.2.9 Stainless Steel Density (Z2CN18-10)

The maximum contents of carbon, silicon, sulfur, and phosphorus are retained. The chromium and nickel contents correspond to the middle of the range. Half of the manganese content is retained and iron is calculated as the balance. Given the low worth on keff of steel structures, the uncertainty of steel composition is assumed to have no impact on keff.

The stainless steel density is given as 7.9 g/cm3. No uncertainty value is provided for stainless steel in the experimental reports. As a consequence, one half of the last digit is retained (0.05 g/cm3) as an uncertainty. The 1σ uncertainty is equal to 0.029 g/cm3 since an equiprobable distribution is assumed.

2.2.10 Screens Densities

At the end of 2010, the titanium screen density was measured by FILAB (France) with helium pycnometry. The uncertainty of the measurements is ±0.0001 g/cm3 (last significant digit). The results of measurements are reported in Table 22.

Table 22: Titanium screens densities.

4A-Ti-005 4A-Ti-010 Density (g/cm3) 4.4910 4.5049 1σ uncertainty 0.002 0.0005

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The 1σ uncertainty shown in Table 22 reported by the experimentalistsa is the standard deviation of measurements. It reflects the standard deviation of the measurements performed for each screen.

To propagate the calculated screen density uncertainty in terms of ∆keff, MORET 4 perturbation calculation using the correlated sampling method were performed; the screen density is varied by ±0.05 g/cm3. The keff variation is then scaled to

the 1σ uncertainty. The results are presented in

Table 23.

Table 23: Density uncertainty propagated in terms of ∆keff.

Experiment

Density variation

in calculation (in g/cm3)

∆keff ×××× 105: keff(+variation)-keff(-variation)

Uncertainty in density

Scaling factor ∆keff ×××× 105

4A-Ti-005 ±0.05 79 0.002 1 2 4A-Ti-010 ±0.05 83 0.0005 1 Negligible

2.2.11 Screen Composition

2.2.11.1 Composition

Two chemical analyses were performed to characterize the two titanium screens on 09/12/2008 in the US during the fabrication process and at the end of 2010 by FILAB company in France. The analyses are consistent for the main elements that are detected above the detection limits. The technique used in France was ICP-OES. The technique used in the U.S. to quantify the elements in the titanium was the Glow Discharge Mass Spectrometry (GDMS). The GDMS technique is more precise than ICP-OES, the detection limit of impurities being far lower. Consequently, the US analysis is retained. The impurities below the detection limit (referred to as undetected impurities) are not modeled as they can potentially be absent from the screen. However, their impact on keff is calculated keeping 100% of the detection limit. These calculations are detailed in 2.2.11.3 and 2.2.11.2. Moreover, some detected impurities (B, Hf, In, Sb, Mg, S, Cl, V, Co, Cu, Ga, Ge, As, Zr, Nb, Mo, Ru, W, Pb, Th, U) whose concentration is very low (see Table 14) are not modeled. No bias is retained. The elements retained in the model are given in Table 24.

Table 24: Retained elements in titanium screens.

Weight % Elements

Titanium 5 mm Titanium 10 mm Fe 0.12 0.14 Cr 0.024 0.024

a Oral communication

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Ti 99.6111 99.6164 Sn 0.0018 0.0034 C 0.016 0.013 N 0.002 0.0017 O 0.19 0.16 Al 0.0015 0.0051 Si 0.011 0.013 P 0.00093 0.0019

Mn 0.0028 0.005 Ni 0.011 0.01

2.2.11.2 Detected Elements

The precision of the measurement of detected elements (by GDMS technique) is not reported in the U.S. analysis. Nevertheless the detected impurities are included in the model, and an uncertainty corresponding to the last digit of each impurity weight in percent (see Section 1.3.8) is taken into account. A variation of the last digit of impurities content is calculated with MORET 4 code using the correlated sampling method. This calculation allows knowing the worth of all impurities. The results of these calculations are reported in Table 25. The results are then scaled to 1σ (divided by √3 since all values are considered equiprobable in the range of the uncertainty).

Table 25: Detected elements uncertainties propagated in terms of ∆keff.

Experiment

Parameter variation in calculation:

(± Last digit of elements content)

∆keff ×××× 105 keff(+variation) – keff(-variation)

Uncertainty in last digit of elements

content

Scaling factor ∆keff ×××× 105

4A-Ti-005 ±1 4 1 √3 1 4A-Ti-010 ±1 5 1 √3 1

2.2.11.3 Undetected Impurities

The impurities, reported to be below a detection limit, are not included in the model. The maximum content of detected impurities depends on the impurity for the American analysis. This content is reported in Table 26.

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Table 26: Detection limit of impurities in titanium experiments.

Elements ppm/weight Elements ppm/weight Li <0.01 Cs <0.01 Cd <0.1 Ba <0.01 Be <0.005 La <0.005 Bi <0.05 Ce <0.005 F <0.5 Pr <0.005

Na <0.01 Nd <0.005 K <0.05 Sm <0.005 Ca <5 Eu <0.005 Sc <0.1 Gd <0.005 Zn <0.1 Tb <0.005 Se <0.05 Dy <0.005 Br <0.1 Ho <0.005 Rb <5 Er <0.005 Sr <3000 Tm <0.005 Y <200 Yb <0.005 Rh <0.1 Lu <0.005 Pd <0.05 Ta <16 Ag <0.1 Re <0.01 Te <0.05 Os <0.01 I <0.01 Ir <0.01 Pt <0.05 Au <0.1 Hg <0.1 Tl <0.01

The effect of all the undetected impurities presented in the chemical analysis in Section 1.3.8 is calculated. An uncertainty of 100% of the detection limit is retained. The impact on reactivity worth of a 100% perturbation on undetected impurities is calculated using MORET 4 perturbation calculations with the correlated sampling method. The results are then scaled to 1σ (divided by √3 since all values are considered equiprobable in the range of the uncertainty).

The uncertainty values are also presented in Table 27.

Table 27: Undetected impurity uncertainties propagated in terms of ∆keff.

Experiment

Parameter variation in calculation (+variation)

∆keff ×××× 105 keff -keff(+variation)

Uncertainty in

undetected impurities

content

Scaling factor ∆keff ×××× 105

4A-Ti-005 100% for all impurities

Negligible 100% √3 Negligible

4A-Ti-010 100% for all impurities

Negligible 100% √3 Negligible

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2.2.12 Stainless Steel Impurities

The stainless steel specifications are given in Reference 1. Chromium and nickel contents are given with an uncertainty value. The uncertainty for manganese and silicon are assumed to be half of the retained value. A MORET 4 calculation using the correlated sampling method is performed to propagate these uncertainties in terms of ∆keff. The variations result in a keff variation of ±0.00001 for all cases, considered as being negligible. As a consequence, the 1σ uncertainty is considered as being negligible.

2.2.13 Temperature and water density

2.2.13.1 Temperature

The temperature uncertainty value was not reported in experimental reports. A value of ±2°C corresponding approximately to the range of variation of the temperature in the reflector is then retained. A ±2°C variation was applied, which, consequently,would modify the water density. The ∆keff corresponding to the total range of variation was then scaled to 1σ by dividing by 32 × .

2.2.13.2 Water Density Value The temperature of the experiments (for density of moderating and reflecting water) is considered to be 21°C. For this temperature, the corresponding water density from the Handbook of Chemistry and Physicsa is 0.99799 g/cm3. No water density uncertainty was reported. However, since a ±2°C uncertainty on temperature is assumed, a 0.05% uncertainty on water density is derived. The effect of a 0.1% variation of the water density is evaluated by performing a MORET 4 perturbation calculation that uses the correlated sampling method. The keff variation is then scaled to the uncertainty (0.05%) and divided by √3 to scale the bounds, assuming uniform probability distribution, to one standard deviation. 2.3 Geometrical Uncertainties

2.3.1 Water Height

The experiments were sub-critical approaches extrapolated to criticality. In general, the level was raised very close to the critical one, such that the final keff was approximately within -β/10 ≈ -65 × 10-5 from criticality. As a consequence, keff was set equal to 1.0000.

Table 1 gives the uncertainty for each experiment (Reference 1); these uncertainties are of statistical and methodological origin.

a Handbook of Chemistry & Physics, 87th edition, 2006-2007.

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The effect on keff of the uncertainty on critical height is calculated by the difference between two APOLLO2-MORET 4 calculations with a small standard deviation (σcalc <0.0001). The deviation applied on water height are lower than ±1 cm to stay within the linearity interval.

2.3.2 Rod Height

A 1σ uncertainty of ±0.04 cm is retained in the fuel rod height. Two independent APOLLO2-MORET 4 direct calculations with a low Monte Carlo standard deviation were performed to assess the impact of a variation of ±2 cm of the rod height. The ∆keff variation was negligible for all cases.

2.3.3 Fissile Column Height

A 1σ uncertainty of ±0.254 cm is retained. Two independent APOLLO2-MORET 4 direct calculations with a low Monte Carlo standard deviation were performed to assess the impact of a variation of ±1 cm of the fissile column height. The ∆keff variation was negligible for all cases.

2.3.4 Cladding Dimensions

Table 4 gives the measured values plus the standard deviation (1σ) for all parameters except for the clad inner diameter, for which only the specification value is given. Manufacturing tolerances give an uncertainty of ±0.005 cm. Variation calculations on each parameter have been carried out. The uncertainty of the outer clad diameter was measured to be 0.000439 cm (1σ), which is the same order as the precision of the measuring device (the palmer, the precision being ±0.0005 cm). A MORET 4 perturbation calculation is performed using the correlated sampling method and varying the outer clad diameter by ±0.0005 cm. The result was then scaled to 1σ (divided by √3 for the measuring device precision). Another MORET 4 perturbation calculation is performed using the correlated sampling method and varying the inner clad diameter by ±0.005 cm. The result was then scaled to 1σ (divided by √3 since a manufacturing tolerance is used).

2.3.5 Rod Positioning

The rod positioning 1σ uncertainty is dealt with in Section 1.2.6. A MORET 4 pertubation calculation was performed to propagate the uncertainty on the gap between the rod and the grid hole. The dimension was modified in the MORET 4 calculations to take into account an increase and a decrease of the gap. The gap between the rod and the grid hole is assumed to vary from 0.030755 cm.

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Sensitivity analysis shows that the rod positioning uncertainty due to the space between the rod clad and the hole is the main contributor to the overall uncertainty originated from the pitch. Nevertheless, the contribution of the different components to the global uncertainty was assessed.

The variation applied on the pitch is 0.030755 cm. Its impact on reactivity is calculated using a MORET 4 perturbation calculation. The effect on keff of the variation is then scaled to 1σ (divided by √3 ) and divided

by N (number of rods in the core: 400 for 4A-Ti-005 and 440 for 4A-Ti-010) contrary to what was done for other parameters. In fact, the external size of the array is limited by the position of grid external holes. As a consequence, all the rods cannot get further from one another of the value of the gap at the same time; the

N can account for that.

The same calculations are used to determine the impact of the hole positioning, grid hole diameter, and rod clad outer diameter uncertainties on both titanium experiments. All results are given in Table 35 and in Table 36.

2.3.6 Screen Dimensions

Two different techniques were used to measure the screens: the laser tracker and the palmer device. The measurements are reported in Table 6. For a consistency purpose and given the low discrepancy between the two types of measurements, it is decided to keep, in the benchmark model, the average of thicknesses given by the palmer device for the two screens. The retained values are reported in Table 28.

Table 28: Measured dimensions of the titanium screens.

Material Configurations Thickness

(cm) Height (cm)

Length (cm)

4A-Ti-005 0.5025 100.0027 36.509 Titanium

4A-Ti-010 1.0032 100.0044 40.2027

Concerning the laser tracker technique, the screens were measured at different positions of a mesh. The given values are the mean values of approximately 60 measurements. Consequently two types of uncertainty are taken into account:

• A precision of 0.015 mm which is associated to each measurement. • A random uncertainty which is the standard deviation of all the measurements. The standard

deviations are tabulated in Table 6. Concerning the thicknesses measurements with the palmer, 60 measurements were also performed at different locations. No uncertainty associated with the technique itself is given. The retained uncertainty combines the dispersion of the measurements and a systematic uncertainty associated with the palmer device, which can be assumed to be equal to ±0.005 mm (half of the last digit). It is to be noted that the discrepancy between this set of measurements and the measurements made with the laser tracker is lower than the laser tracker precision.

The applied deviation on thicknesses is ±0.12 mm for 4A-Ti-005 and for 4A-Ti-010. It is to be noted that the uncertainty on screen length and height is assumed to be negligible.

The effect on keff of the uncertainty in screen thicknesses is evaluated by the difference between two direct APOLLO2-MORET 4 calculations. The results of those calculations are reported in Table 29.

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These calculations are used to determine the impact of the random uncertainty, and the systematic uncertainty:

• Random uncertainty (1σ : ±0.0009 cm for 4A-Ti-005, ±0.0010 cm for 4A-Ti-010). • Systematic uncertainty (1σ : ±0.0005 cm for both titanium experiments).

Table 29: Thicknesses uncertainties propagated in terms of ∆keff.

Experiment

Thickness variation in calculation

(mm)

∆keff ×××× 105 keff(+variation) -keff(-variation)

Uncertainty in Thickness

(mm)

Scaling factor

∆keff ×××× 105

Total uncertainty ∆keff x 105

Random uncertainty

0.0090 1 8 4A-Ti-005 ±0.12 210

Systematic uncertainty

0.0050 1 5 10

Random uncertainty

0.0100 1 6 4A-Ti-010 ±0.12 148

Systematic uncertainty

0.0050 1 3 7

2.3.7 Positioning of Arrays and screens

During their assembling, the titanium screens are slipped into guidance rails. The tolerance interval on the slit in which the screens are introduced is [+0.1 mm; +0.5 mm]. Moreover, the assembling of the two screens by means of the groove requires a perfect perpendicularity of the two assembled screens. The UO2 rods baskets are positioned in order to have perfect contact between the grids and the titanium screens. Considering the maximum shift between the rod arrays and the screen, the arrays’ positioning uncertainty is estimated to be 0.4 mm. It corresponds to three sources of uncertainty:

• The uncertainty corresponding to how the array grids are stuck onto the screen (0.15 mm) • The uncertainty due to the positioning of the first row of holes in the grid (0.15 mm) • The uncertainty due to the flatness of the grid (0.1 mm).

For each experiment two APOLLO2-MORET 4 calculations were performed: one without gap (in that case, the grid is in contact with the screen and the distance between the outermost row of rods and the screen is half a pitch) and another with a gap between screens and arrays (see Figure 17). The gap has to be sufficient so that ∆keff is higher than the Monte-Carlo standard deviation. The calculation gap retained is 1 mm for all the experiments. The effect of a asymetric postioning of baskets has also been investigated.

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Figure 17: Positioning of arrays for 4A-Ti-005 and 4A-Ti-010 experiments.

The keff variation is then scaled to the uncertainty (0.4 mm) and divided by 3 to be scaled to 1σ since all values are considered equiprobable within the uncertainty range. Table 30 presents the results of these calculations for both titanium experiments.

Table 30: keff uncertainties caused by the array positioning uncertainties.

Experiment

Gap between screen and

array variation in calculation

(+ variation) (mm)

∆keff × 105 keff(without variation)-

keff(+variation)

Uncertainty in Gap (mm)

Scaling factor

∆keff × 105

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4A-Ti-005 1 117 0.4 √3 27

4A-Ti-010 1 83 0.4 √3 19

The impact of asymetry in the positioning of grids against the screen was also investigated. APOLLO2-MORET 4 calculations were performed moving separately the four arrays of UO2 rods. The results are reported in Table 31.

Table 31: Impact of Assymmetry on the positioning uncertainty.

Shift of position of UO2 arrays in cm Upper right array shift

Lower left array shift

Lower right array shift

Upper left array shift

keff keff –keff

(reference) in pcm

0 0 0 0 1.01055 (reference) 0

0.04 0 0 0 1.01041 -14

0.1 0 0 0 1.00992 -63

0.04 0 0.04 0 1.01013 -42

0.1 0 0.1 0 1.00984 -71

0.04 0.04 0 0 1.0103 -25

0.1 0.1 0 0 1.00961 -94

0.1 0 0 0.1 1.00967 -88

0.1 0.1 0.1 0 1.0095 -105

0.1 0 0.1 0.1 1.00924 -131

0.1 0.1 0 0.1 1.00962 -93

0.1 0.1 0.1 0.1 1.00936 -119

It is shown that the impact on reactivity is associated with the way the arrays are moved. However, the impact is close to maximum when the four arrays are moved the same distance together.

2.3.8 Repeatability and Reproducibility Experiments

Preliminary sensitivity/uncertainty calculations were performed in order to evaluate the impact on keff of specific uncertainties (such as the rod positioning and the screen positioning). These calculations lead to imposing strong constraints on the experimental device and proposing reproducibility experiments in order to reduce the experimental uncertainties. Reproducibility experiments can be divided as follows:

• Repeatability experiments (Rv), which consist of a new sub-critical approach after water draining without any change in the configuration. This kind of experiments will give information about the uncertainties on the water height measurement and the extrapolation method.

• Reproducibility experiments (Rb), which consist of a new sub-critical approach after: (S1) Water draining and removal of the experimental device (support pedestal and lattices) without

any change in the configuration, allowing the estimation of the uncertainty in rod positioning due to the gap between grid holes and rods.

(S2) Water draining, removal of the experimental device and moving lattice baskets, which highlights the uncertainty in lattice positioning.

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(S3) Water draining, removal of the experimental device (support pedestal and lattices) and change of rods in order to estimate the uncertainty in rod sampling; notice that the rods are issued from a completely different batch.

(S4) Water draining, removal of the experimental device, the UO2 rods and the tested screens to evaluate uncertainty in screen positioning. It should be mentioned that the batch of UO2 rods is different from S2, S1, Rv, and reference experiments.

The repeatability and reproductibility experiments give new critical water heights values. The keff value of the repeatability or reproducibility experiment is calculated and then compared to the keff value of the original experiment.

Table 32: Reproducibility and repeatability experiments results (APOLLO2-MORET 4 and MORET 5, Monte Carlo uncertainty: 1σ = ± 0.00010).

APOLLO2-MORET 4 MORET 5 Repeatability and

reproducibility experiments

hc (cm) ±2σσσσ ∆∆∆∆hc (cm)

(repeatability-reference)

∆keff keff(hcTi5) - keff(hc repeatablility)

∆keff keff(hcTi5) - ∆keff(hc

repeatablility) 4A-Ti-005 70.063 ± 0.045 0 0 0

4A-Ti-005(Rv) 70.048 ± 0.039 -0.015 -0.00015 0.00013 4A-Ti-005-Rb(S2) 70.094 ± 0.054 0.031 0.00016 0.00002 4A-Ti-005-Rb(S4) 69.742 ± 0.055 -0.321 0.00036 0.00059

R4A-Eau-005 59.982 ± 0.082 0 0 0 R4A-Eau-005-Rb(S2) 60.010 ± 0.084 0.028 000013 -0.00020 It can be noted that, except for 4A-Ti-005-Rb(S4) experiment, the discrepancies between repeatability/reproducibility experiments and the reference experiment are within the 2σ uncertainty on critical heights associated with the extrapolation method and the level measurement device.

The results confirm that the uncertainty in rod positioning and critical water height are small or negligible, as confirmed with independent calculations in Sections 2.3.5 and 2.3.1, respectively. However, a significant but small effect on rod sampling and/or screen positioning (S4 reproducibilities) can be highlighted. The effect of array positioning with respect to the screen is evaluated in Section 2.3.7. The effective uncertainties due to variation in the properties of the fuel rods are summarized in Tables 32 and 33. The repeatability/reproducibility experiments are not unique benchmark experiment configurations in comparison with 4A-Ti-005, even if they constitute new critical configurations. For 4A-Ti-005, it is proposed to average the water heights of the reference experiment and the Rv and S2 experiments, and then average this water height with the S4 experiment. The aim of that treatment is to clearly make a distinction between the Rv and S2 experiments and the S4 experiment, for which the sample of UO2 rods is different, which introduces an effect on reactivity. The obtained critical heights are reported in Table 33. The retained critical height uncertainty for the 4A-Ti-005 experiment is the highest amongst the reference, Rv, S2, and S4 experiments. Nevertheless, no additional uncertainty related to the dispersion of critical height amongst the experiments should be added since they are already summed up in other parameter uncertainties (positioning of baskets, rod sampling). The calculated values are consistent with the ∆keff effects of Table 32 corresponding to the ∆hc.

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Similarly, for the R4A-Eau-005 and R4A-Eau-005-Rb(S2) experiments, it is proposed to average the critical heights for the same reasons (see Table 33).

Table 33: Retained critical heights.

Repeatability and reproducibility

experiments hc (cm) ±2σσσσ

R4A-Eau-005 59.996 ± 0.086 R4A-Eau-010 59.793 ± 0.091

4A-Ti-005 69.905 ± 0.055 4A-Ti-010 89.483 ± 0.028

2.4 Reactivity Sensitivity Calculations

Sensitivity calculations are carried out with either one APOLLO2-MORET 4 (correlated sampling method) or two independent APOLLO2-MORET 4 Monte Carlo calculations. The uncertainty effect on keff is determined directly through a correlated sampling method or by the difference of two independent direct MORET 4 calculations (with a small Monte Carlo deviation).

A comparison between continuous energy Monte Carlo MORET 5 (under validation ) code and APOLLO2-MORET 4 code was performed. The results are provided in APPENDIX D. A general good agreement is obtained between calculated results obtained using either MORET 5 or APOLLO2-MORET 4 codes.

Table 34a and b summarizes the evaluation of experimental uncertainties for all the parameters discussed in Sections 2.2 and 2.3. The uncertainties in keff corresponding to most parameters are presented in Table 35 for 4A-Ti-005, in Table 36 for 4A-Ti-010, in Table 37 for R4A-Eau-005, and in Table 38 for R4A-Eau-010.

For reference experiments (R4A-Eau-005 and R4A-Eau-010), the uncertainties pertaining to the rods are not calculated. The uncertainties of the corresponding configuration with a screen are retained. However, for what is specific to the reference configuration (critical water height, distance between arrays), calculations are performed.

The individually evaluated uncertainties were summed in quadrature to obtain the total uncertainty in each experiment. The most significant uncertainty is in the density of the UO2 fuel. All four experiments were determined to represent acceptable benchmark experiments.

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Table 34a: Material uncertainties.

Parameter Identification Mean Value

Uncertainties in Parameter

Type of Uncertainty

(A or B)

νννν Number

of Degrees of

Freedom

Number of Standard Deviations Associated with the

Uncertainty

Standard Deviation

(1σσσσ)

Uranium Isotopic Contents (at.%):

234U 235U 236U 238U

0.0307 4.79525 0.1373

95.03675

0.001 0.004 0.001 0.02

A ∞ 2

0.0005 0.002 0.0005 0.01

UO2 Density (g/cm3) - random 10.38 0.073 A ∞ 1 0.073/√N UO2 Density (g/cm3) -

systematic 10.38 0.076 B ∞ 1 0.076

UO2 Detected Impurities 100% B ∞ √3 100%/√3 UO2 Undetected Impurities 6.28.10-6 100%(LD) B ∞ √3 100%/√3

Water Density (g/cm3) 0.99820 0.05% B ∞ √3 0.05/√3

Screen Density 4.491 and

4.5049 0.002 and

0.0005 A ∞ 1

0.002 and 0.0005

Screen Undetected Impurities 0 100%(LD) B ∞ √3 100%/√3 Screen Detected Elements

(last digit of elements content in %)

±1 B ∞ √3 1/√3

Water Impurities 0 100% B ∞ √3 100%/√3 Stainless Steel Density (g/cm3) 7.9 0.05 B ∞ √3 0.05/√3

Stainless Steel Content (Cr) 18% 1% B ∞ √3 1%/√3 Stainless Steel Content (Ni) 10% 1% B ∞ √3 1%/√3 Stainless Steel Content (Si) 0.5% 0.5% B ∞ √3 0.5%/√3

Stainless Steel Content (Mn) 1% 1% B ∞ √3 1%/√3

Zircaloy Density (g/cm3) 6.55 0.005 B ∞ √3 0.005/√3

O/U Stoichiometry 2.000 0.001 A ∞ 1 0.001 Water Temperature (°C) 20 2 B ∞ √3 2/√3

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Table 34b: Geometrical uncertainties.

Parameter Identification Mean Value

Uncertainties in Parameter

Type of Uncertainty

(A or B)

νννν Number

of Degrees

of Freedom

Number of Standard Deviations Associated with the

Uncertainty

Standard Deviation

(1σσσσ)

Fuel Pellet Diameter - measurement (cm)

0.00176 A 52 1 0.00176

Fuel Pellet Diameter - systematic (cm)

0.78919 0.005 B ∞ √3 0.005/√3

Fissile Column Height (cm) 89.765 0.254 A 1260 1 0.254

Clad Outer Diameter measurement (cm)

0.9492 0.000439 A 299 1 0.000439

Clad Outer Diameter systematic (cm)

0.9492 0.0005 B ∞ √3 0.0005/√3

Clad Inner Diameter (cm) 0.836 0.005 B ∞ √3 0.005/√3

Rod Height (cm) 102.082 0.04 B ∞ √3 0.04/√3

Critical Water Height (cm) Between 70 and 90

From 0.028 to 0.055 A None 2 From

0.014 to 0.028 Rod Location – Gap rod/Grid hole (cm)

1.6 0.01 B ∞ √3 0.01/√3√N(a)

Rod Location – Grid hole diameter (cm)

1.6 0.01 B ∞ √3 0.01/√3√N(a)

Rod Location – grid hole positioning (cm)

1.6 0.030755 B ∞ √3 0.30755/√3√N(a)

Rod Location – rod diameter (cm)

1.6 0.0005 B ∞ √3 0.0005/√3√N(a)

Systematic uncertainty

0.005 0.005 Titanium Screen Thickness

(mm) 5 and 10

Random uncertainty

0.009 to 0.010

A ∞ 1 0.009 to 0.010

Position of Arrays (cm) 0.04 B ∞ √3 0.04/√3 (a) N is the number of rods in the rod arrays

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Table 35: Results of sensitivity calculations, titanium experiment (4A-Ti-005).

Parameter Identification Parameter

Variation in Calculation

Type of Calculation(a)

∆keff ×××× 105 keff(+variation)

– keff

(-variation)

Uncertainty in Parameter Scaling factor ∆keff × 105555

Uranium Isotopic Contents

235U (at.%) ±0.004 A2M4 CS 38 0.004 2 10

UO2 Density (g/cm3) – random 0.073 √400 6

UO2 Density (g/cm3) – systematic ±0.073 A2M4 CS 220

0.076 1 115

UO2 detected Impurities ±100% A2M4 CS 5 100% √3 2

UO2 undetected Impurities 100% A2M4 CS 42 100% √3 24

Water Density (g/cm3) ±0.1% A2M4 CS 53 0.05% √3 7

Water impurities 100% A2M4 CS Negligible 100% √3 Negligible

Fuel Pellet Diameter measurement (cm)

±0.01 A2M4 CS 27 0.00176 1 5

Fuel Pellet Diameter systematic (cm)

±0.01 A2M4 CS 27 0.005 √3 4

Clad Outer Diameter measurement (cm)

±0.0005 A2M4 CS 19 0.000439 1 8

Clad Outer Diameter systematic (cm)

±0.0005 A2M4 CS 19 0.0005 √3 5

Clad Inner Diameter (cm) ±0.005 A2M4 CS 13 0.005 √3 4

Zircaloy Density (g/cm3) ±0.05 A2M4 CS 42 0.005 √3 Negligible

AG3 density (g/cm3) ±0.005 A2M4 CS Negligible 0.005 √3 Negligible

Stainless Steel density ±0.05 A2M4 CS Negligible 0.05 √3 Negligible

Stainless Steel impurities 100% A2M4 CS Negligible 100% √3 Negligible

O/U Stoichiometry ±0.01 A2M4 CS Negligible 0.001 1 Negligible

Rod height (cm) ±2 A2M4 DC Negligible 0.04 √3 Negligible

Fissile Column Height (cm) ±1 A2M4 DC Negligible 0.254 1 Negligible

Critical Water Height (cm) ±0.6 A2M4 DC 150 0.045 2 3

Rod Location – Grid Hole Positioning (cm) – Gap Grid/Rod

0.030755 10

Rod Location – Grid Hole Positioning (cm) – Hole Position

0.01 7

Rod Location – Grid Hole Positioning (cm) – Grid Diameter

0.01 7

Rod location – Grid Hole Positioning (cm) – Rod Diameter

±0.030755 A2M4 CS 658

0.0005

√3×√400

Negligible

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Table 35: Results of sensitivity calculations, titanium experiment (4A-Ti-005) (continued)

Parameter Identification Parameter

Variation in Calculation

Type of Calculation(a)

∆keff ×××× 105 keff(+variation) –

keff

(-variation)

Uncertainty in Parameter

Scaling factor

∆keff × 105555

A2M4 DC Random

uncertainty 0.0009 1 8

Screen Thickness (cm) ±0.012 A2M4 DC

210 Systematic uncertainty

0.0005 1 10

Screen Density (g/cm3) ±0.05 A2M4 CS 79 0.002 1 2

Screen Detected Elements (last digit of elements content in %)

±1 A2M4 CS 4 1 √3 2

Screen Undetected Impurities 100% A2M4 CS Negligible 100% √3 Negligibl

e

Position of Rod arrays (cm) 0.1 A2M4 DC 117 0.04 √3 27

Temperature (°C) ±2 A2M4 CS 24 2 √3 7

OVERALL UNCERTAINTY 124 (a) A2M4 CS: APOLLO2-MORET 4 code using the correlated sampling method A2M4 DC: two APOLLO2-MORET 4 direct calculations (Monte Carlo standard deviation)

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Table 36: Results of sensitivity calculations, titanium experiment (4A-Ti-010).

Parameter Identification Parameter

Variation in Calculation

Type of Calculation(a)

∆keff ×××× 105 keff(+variation)

– keff

(-variation)

Uncertainty in Parameter

Scaling factor

∆keff × 105555

Uranium Isotopic Contents

235U (at.%) ±0.004 A2M4 CS 40 0.004 2 10

UO2 Density (g/cm3) - random 0.073 √440 5

UO2 Density (g/cm3) - systematic ±0.073 A2M4 CS 196

0.076 1 102

UO2 detected Impurities ±100% A2M4 CS 5 100% √3 2

UO2 undetected Impurities 100% A2M4 CS 42 100% √3 24

Water Density (g/cm3) ±0.1% A2M4 CS 53 0.05% √3 7

Water impurities 100% A2M4 CS Negligible 100% 1 Negligible Fuel Pellet Diameter measurement

(cm) ±0.01 A2M4 CS 28 0.00176 1 5

Fuel Pellet Diameter systematic (cm)

±0.01 A2M4 CS 28 0.005 √3 4

Clad Outer Diameter measurement (cm)

±0.0005 A2M4 CS 16 0.000439 1 8

Clad Outer Diameter systematic (cm)

±0.0005 A2M4 CS 16 0.0005 √3 5

Clad Inner Diameter (cm) ±0.005 A2M4 CS 13 0.005 √3 4

Zircaloy Density (g/cm3) ±0.05 A2M4 CS 42 0.005 √3 Negligible

AG3 density (g/cm3) ±0.005 A2M4 CS Negligible 0.005 √3 Negligible

Stainless Steel density ±0.05 A2M4 CS Negligible 0.05 √3 Negligible

Stainless Steel impurities 100% A2M4 CS Negligible 100% √3 Negligible

O/U Stoichiometry ±0.01 A2M4 CS Negligible 0.001 1 Negligible

Rod Height (cm) ±2 A2M4 DC Negligible 0.04 √3 Negligible

Fissile Column Height (cm) ±1 A2M4 DC Negligible 0.254 1 Negligible

Critical Water Height (cm) +0.282/- 0.6 A2M4 DC 33 0.028 2 Negligible Rod Location – Grid Hole

Positioning (cm) – Gap Grid/Rod 0.030755 10

Rod Location – Grid Hole Positioning (cm) – Hole Position

0.01 7

Rod Location – Grid Hole Positioning (cm) – Grid Diameter

0.01 7

Rod location – Grid Hole Positioning (cm) – Rod Diameter

±0.030755 A2M4 CS 728

0.0005

√3×√440

Negligible

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Table 36: Results of sensitivity calculations, titanium experiment (4A-Ti-010) (continued)

Parameter Identification Parameter

Variation in Calculation

Type of Calculation(a)

∆keff ×××× 105 keff(+variation)

– keff

(-variation)

Uncertainty in Parameter

Scaling factor

∆keff × 105555

A2M4 DC Random

uncertainty 0.0010 1 6

Screen Thickness (cm) ±0.012 A2M4 DC

148 Systematic uncertainty

0.0005 1 7

Screen Density (g/cm3) ±0.05 A2M4 CS 83 0.0005 1 Negligible Screen Detected Elements (last digit

of elements content in %) ±1 A2M4 CS 5 1 √3 2

Screen Undetected Impurities 100% A2M4 CS Negligible 100% √3 Negligible

Position of Rod arrays (cm) 0.1 A2M4 DC 83 0.04 √3 19

Temperature (°C) ±2 A2M4 CS 24 2 √3 7

OVERALL UNCERTAINTY 110 (a) A2M4 CS: APOLLO2-MORET 4 code using the correlated sampling method A2M4 DC: two APOLLO2-MORET 4 direct calculations (Monte Carlo standard deviation)

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Table 37: Results of sensitivity calculations, reference experiment (R4A-Eau-005).

Parameter Identification Parameter

Variation in Calculation

Type of Calculation(a)

∆keff ×××× 105 keff(+variation) –

keff

(-variation)

Uncertainty in Parameter

Scaling factor

∆keff × 105555

Uranium Isotopic Contents

235U (at.%) ±0.004 A2M4 CS 38 0.004 2 10

UO2 Density (g/cm3) - random 0.073 √288 6

UO2 Density (g/cm3) - systematic ±0.073 A2M4 CS 220

0.076 1 115

UO2 detected Impurities ±100% A2M4 CS 5 100% √3 2

UO2 undetected Impurities 100% A2M4 CS 42 100% √3 24

Water Density (g/cm3) ±0.1% A2M4 CS 53 0.05% √3 7

Water impurities 100% A2M4 CS Negligible 100% 1 Negligible

Fuel Pellet Diameter measurement (cm)

±0.01 A2M4 CS 27 0.00176 1 5

Fuel Pellet Diameter systematic (cm)

±0.01 A2M4 CS 27 0.005 √3 4

Clad Outer Diameter measurement (cm)

±0.0005 A2M4 CS 19 0.000439 1 8

Clad Outer Diameter systematic (cm)

±0.0005 A2M4 CS 19 0.0005 √3 5

Clad Inner Diameter (cm) ±0.005 A2M4 CS 13 0.005 √3 4

Zircaloy Density (g/cm3) ±0.05 A2M4 CS 42 0.005 √3 Negligible

AG3 density (g/cm3) ±0.005 A2M4 CS Negligible 0.005 √3 Negligible

Stainless Steel density ±0.05 A2M4 CS Negligible 0.05 √3 Negligible

Stainless Steel impurities 100% A2M4 CS Negligible 100% √3 Negligible

O/U Stoichiometry ±0.01 A2M4 CS Negligible 0.001 1 Negligible

Rod height (cm) ±2 A2M4 DC Negligible 0.04 √3 Negligible

Fissile Column Height (cm) ±1 A2M4 DC Negligible 0.254 1 Negligible

Critical Water Height (cm) ±0.6 A2M4 DC 186 0.086 2 7

Rod Location – Grid Hole Positioning (cm) – Gap Grid/Rod

0.030755 11

Rod Location – Grid Hole Positioning (cm) – Hole Position

0.01 4

Rod Location – Grid Hole Positioning (cm) – Grid Diameter

0.01 4

Rod location – Grid Hole Positioning (cm) – Rod Diameter

±0.030755 A2M4 CS 658

0.0005

√3×√288

Negligible

Position of Rod arrays (cm) 0.1 A2M4 DC 108 0.04 √3 13

Temperature (°C) ±2 A2M4 CS 24 2 √3 7

OVERALL UNCERTAINTY 121 (a) A2M4 CS: APOLLO2-MORET 4 code using the correlated sampling method A2M4 DC: two APOLLO2-MORET 4 direct calculations (Monte Carlo standard deviation)

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Table 37: Results of sensitivity calculations, reference experiment (R4A-Eau-010).

Parameter Identification Parameter

Variation in Calculation

Type of Calculation(a)

∆keff ×××× 105 keff(+variation) –

keff

(-variation)

Uncertainty in Parameter Scaling factor ∆keff × 105555

Uranium Isotopic Contents

235U (at.%) ±0.004 A2M4 CS 40 0.004 2 10

UO2 Density (g/cm3) - random 0.073 √288 6 UO2 Density (g/cm3) -

systematic ±0.073 A2M4 CS 196

0.076 1 102

UO2 detected Impurities ±100% A2M4 CS 5 100% √3 2

UO2 undetected Impurities 100% A2M4 CS 42 100% √3 24

Water Density (g/cm3) ±0.1% A2M4 CS 53 0.05% √3 7

Water impurities 100% A2M4 CS Negligible 100% 1 Negligible

Fuel Pellet Diameter measurement (cm)

±0.01 A2M4 CS 28 0.00176 1 5

Fuel Pellet Diameter systematic (cm)

±0.01 A2M4 CS 28 0.005 √3 4

Clad Outer Diameter measurement (cm)

±0.0005 A2M4 CS 16 0.000439 1 8

Clad Outer Diameter systematic (cm)

±0.0005 A2M4 CS 16 0.0005 √3 5

Clad Inner Diameter (cm) ±0.005 A2M4 CS 13 0.005 √3 4

Zircaloy Density (g/cm3) ±0.05 A2M4 CS 42 0.005 √3 Negligible

AG3 density (g/cm3) ±0.005 A2M4 CS Negligible 0.005 √3 Negligible

Stainless Steel density ±0.05 A2M4 CS Negligible 0.05 √3 Negligible

Stainless Steel impurities 100% A2M4 CS Negligible 100% √3 Negligible

O/U Stoichiometry ±0.01 A2M4 CS Negligible 0.001 1 Negligible

Rod Height (cm) ±2 A2M4 DC Negligible 0.04 √3 Negligible

Fissile Column Height (cm) ±1 A2M4 DC Negligible 0.254 1 Negligible

Critical Water Height (cm) ±0.6 A2M4 DC 208 0.091 2 8 Rod Location – Grid Hole

Positioning (cm) – Gap Grid/Rod

0.030755 12

Rod Location – Grid Hole Positioning (cm) – Hole

Position 0.01 4

Rod Location – Grid Hole Positioning (cm) – Grid

Diameter 0.01 4

Rod location – Grid Hole Positioning (cm) – Rod

Diameter

±0.030755 A2M4 CS 728

0.0005

√3×√288

Negligible

Position of Rod arrays (cm) 0.1 A2M4 DC 134 0.04 √3 16

Temperature (°C) ±2 A2M4 CS 24 2 √3 7

OVERALL UNCERTAINTY 109 (a) A2M4 CS: APOLLO2-MORET 4 code using the correlated sampling method A2M4 DC: two APOLLO2-MORET 4 direct calculations (Monte Carlo standard deviation)

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2.5 Reactivity worth of screens

MIRTE experiments were designed in a such way that they present a sufficient reactivity worth of screens in the configuration. This condition is paramount when evaluating the bias of material screens. The reactivity worth of screens is calculated using either APOLLO2-MORET 4 or KENO-V.a codes and replacing the screen either by air or water. The Monte Carlo standard deviation of both calculations is 0.00033. The results are reported in Table 38.

Table 38: Reactivity worth of screens.

Experiment Code Screen replaced by Air Reactivity worth of screen (pcm)

Screen replaced by Water

Reactivity worth of screen (pcm)

KENO-V.a -6370 -7950 4A-Ti-005

APOLLO2-MORET 4

-5800 -7700

KENO-V.a -8670 -11190 4A-Ti-010

APOLLO2-MORET 4

-8000 -11000

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3.0 BENCHMARK SPECIFICATIONS

3.1 Description of Model

The benchmark-model geometry is shown in Figure 19 through 26. Model simplifications are described below. Due to the large amount of water around the core and the small reactivity effect of the rods above the water, the concrete room and the steel tank walls are omitted. The effective bias is assumed to be negligible. The baskets structure (tubes, feet, plates) and the frame of the screens are made of AG3 aluminum alloy; the tubes of the basket and frame structures are hollow and filled with water. The worth of each of these devices has been assessed for 4A-Ti-005 configuration (see Table 39). These devices are omitted from the model and a bias is applied on the benchmark model. It is calculated using APOLLO2-MORET 4 code; two calculations are performed: one with the detailed model and another with the simplified benchmark model. The standard deviation of the Monte Carlo calculation is ±0.00010. The biases are reported in Table 41.

Table 39: Simplification calculations (calculations performed for Case 1).

Part omitted APOLLO2-MORET 4 (172-group, CEA93V6)

∆keff(a) (pcm)

σ Monte-Carlo (pcm)

Support pedestal tubes -18

Tank -11

Basket structure +6

Frame of screen -2

Base of array +17

Reinforcement base +10

Part of the grid without holes +19

All omitted part -37 (b)

10

(a) Difference between keff with component and keff without component. (b) Summation of the individual simplifications in the table is not equivalent to the

effective bias calculated with the omission of all parts. There is a large Monte Carlo statistical uncertainty compared to the magnitude of many of these simplifications and possible correlation effects exist between individual omissions.

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Table 40: Biases for the bechmark models.

Cases

Bias ± uncertainty APOLLO2-MORET 4 (172-group, CEA93V6)

(pcm)

1 -37 ± 12

2 -64 ± 21

3 28 ± 9

4 -55 ± 18

Given the relatively low worth of the biases, the related uncertainties are assumed to be ±30% of the bias value. The springs in the fuel rods are not included in the benchmark models; no bias was evaluated because they are not significant in terms of reactivity. Rod plugs can also be replaced by cylinder-shaped plugs for calculation: the bottom plug is replaced by a 1.18-cm-high cylinder by keeping the mass constant, and the top plug is replaced by a 1.468-cm-high cylinder, both with a 0.949-cm diameter (see APPENDIX C). The impact on reactivity of such simplifications is negligible. Only the three fuel impurities measured over the detection limit are included in the models. The impact on keff of impurities below this detection limit is studied in Section 2.2.4. The homogenization process is described in APPENDIX C. Because the effects of homogenization have not been thoroughly evaluated, and although it is known that this effect is negligible, the homogenized zones are not proposed in the benchmark model. The parts of the lower grid not occupied by UO2 rods are not described exactly; an homogenization of the AG3 aluminum alloy of the grid and water is proposed for the lower grids and an homogenization of the AG3 aluminum alloy of the grid and air is proposed for the upper grid. Calculations demonstrated that the effect of homogenization is negligible. The AmBe source, liminimeter, and neutron counters (sufficiently far from the core) are not modeled. They are assumed to lead to a negligible bias. The fuel pellet diameter is rounded to 0.7892 cm, which led to a negligible bias. The outer clad diameter is rounded to 0.949 cm, which led to a negligible bias. Concerning titanium screens, some detected impurities are not modeled. As explained in Section 2.2.11.1, this led to a negligible bias. No bias related to the non-modeling of thermocouples has been established.

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3.2 Dimensions

The model comprises the following parts surrounding the baskets:

• The support pedestal, reduced to the Z2CN18-10 stainless steel support plate, 186 cm × 186 cm and 2.5 cm thick.

• The water, 27.75 cm thick beneath the support plate. • The water inside and around the fuel arrays under the critical level (see Table 41). • The air inside and around the fuel arrays over the critical level. • The arrays of fuel rods described in Figure 20, 22, 24, and 26 (rods characteristics are given in Table

42 and Figure 18). The bottom of the fissile column is 1.18 cm above the bottom of fuels rods. • The cruciform screen between the rods’ arrays (see Figure 20, 22, 24, and 26), when necessary

(configurations with screens).

Table 41: Benchmark data for titanium screen experiments and their references.

Case Experiment Array Geometry

(nx × ny) Critical Height,

Hc (cm) 1 4A-Ti-005 10 × 10 69.905

2 4A-Ti-010 11 × 10 89.483

3 R4A-Eau-005 9 × 8 59.996

4 R4A-Eau-010 9 × 8 59.793 (a) Section 2.3.8 summarizes how the final benchmark critical heights were

obtained.

The baskets comprise the lower and upper grids of AG3 aluminum alloy. The distance from the top surface of the lower grid to the bottom surface of the upper grid is 97.5 cm.The four square shaped grids measure 24 × 24 cm and are 0.4 cm thick. The parts of the lower grids and the upper grids without rods are homogenized zones of AG3 aluminum alloy and water (for lower grids) or air (for upper grids) (see Table 45). The holes diameters are set equal to 0.98 cm.

The bottom of the screens is 6.7 cm above the support plate of the pedestal.

As the bottom plugs have been cylindrized, the bottom of the fuel rods array is 7.32 cm above the support plate. The fuel rods’ dimensions are given in Table 42. The water critical heights (Hc) and the array dimensions are given in Table 41. A description of the rods is given in Figure 18. It is to be noted that the bottom of the fissile column coincides exactly with the top of the bottom grid in Figures 19, 21, 23, and 25.

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Table 42: Geometrical data for fuel rods.

Fuel Diameter 0.7892 cm

Clad Inner Diameter 0.836 cm

Clad Outer Diameter 0.949 cm

Fissile Column Height 89.765 cm

Bottom Plug Height(a) 1.18 cm

Top Plug Height(a) 1.468 cm

Spring Zone Height 9.049 cm

Total Rod Height(a) (Fissile Column Height + Spring Zone

Height + Top and Bottom Plug Heights) 101.462 cm

Lattice Pitch 1.6 cm

Distance between Surface of the Screens and the Centers of the Adjacent Fuel Rods

(Half Pitch) 0.8 cm

(a) Plugs are replaced by cylinder-shaped plugs (see the first paragraph of APPENDIX C).

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1.18

Upper plug (Zircaloy 4)

Clad (Zircaloy 4)

Clad (Zircaloy 4)

Diameter = 0.949

Water

Fuelpellets

not to scale

Air

89.765

HC

Air

Dimensions in cm

Lower plug (Zircaloy 4)

Pellet diameter = 0.7892

~~

~~

~~

9.049

0.836

1.468

Figure 18: UO2 rod.

The screen dimensions reported in Table 43 are derived from Table 6 (see discussion in Section 2.3.6 and Figure 16).

Table 43: Experiment screen dimensions.

Case Experiment Thickness, e (cm) Length, L (cm) Height, H (cm)

1 4A-Ti-005 0.5025 36.509 100.0027

2 4A-Ti-010 1.0032 40.2027 100.0044

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A general schematic of the benchmark configurations is shown in Figure 19 to Figure 27 . The critical water height, HC, and the array size, nx and ny, are taken from Table 41. The screen thickness or distance between the arrays (for reference experiments), e; height, H; and length, L; are taken from Table 43.

Steel plate (186 x 186 x 2.5)

Air

Detail A

Water

Bottom grid A 324 x 24 x 0.4

G

Bottom grid0.41.18

7.32

Detail A

186

140

97.5*

30.25

6.7

0.98

H

e: thickness of the screenH: height of the screenH : water critical heightc

U rodO2

Titanium screen

189.7

Pedestal2.5

Drawing not to scaleDimensions in cm

11-GA50002-65-1

e

Hc

Top grid AG3 24 x 24 x 0.4

Fue

l col

umn

heig

ht 8

9.76

5

* Distance from top of bottom grid to bottom of top grid

Figure 19: Benchmark model - Case 1 (lateral view).

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Titanium screen

L

Water or air

e

e: thickness of the screen: 0.5025 cmL: length of the screenArray size: 10 x 10Total number of fuel rods: 400

Drawing not to scaleDimensions in cm

11-GA50002-65-2

189.7

189.7

Figure 20: Benchmark model – Case 1 (top view).

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Steel plate (186 x 186 x 2.5)

Top grid AG3 24 x 24 x 0.4

Air

Detail A

Water

Bottom grid A 324 x 24 x 0.4

G

Bottom grid0.41.18

7.32

Detail A

186

140

30.25

6.7

0.98

H

e: thickness of the screenH: height of the screenH : water critical heightc

U rodO2

Titanium screen

189.7

Pedestal2.5

Drawing not to scaleDimensions in cm

11-GA50002-65-3

e

Hc

97.5*

* Distance from top of bottom grid to bottom of top grid

Fue

l col

umn

heig

ht 8

9.76

5

Figure 21: Benchmark model - Case 2 (lateral view).

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L

Water or air

189.7

e

e: thickness of the screen: 1.0032 cmL: length of the screenArray size: 11 x 10Total number of fuel rods: 440

189.7

Drawing not to scaleDimensions in cm

11-GA50002-65-4

Titanium screen

Figure 22: Benchmark model - Case 2 (top view).

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Steel plate (186 x 186 x 2.5)

Air

Detail A

Water

Bottom grid A 324 x 24 x 0.4

G

Bottom grid0.41.18

7.32

Detail A

186

140

97.5*

30.25

0.98

e: separation between arraysH: height of the screenH : water critical heightc

U rodO2

189.7

Pedestal2.5

Drawing not to scaleDimensions in cm

11-GA50002-65-6

e

Hc

Top grid AG3 24 x 24 x 0.4

Fue

l col

umn

heig

ht 8

9.76

5

* Distance from top of bottom grid to bottom of top grid

Figure 23: Benchmark model - Case 3 (lateral view).

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Water or air

189.7

e: separation between arrays: 0.5 cmArray size: 9 x 8Total number of fuel rods: 288

189.7

Drawing not to scaleDimensions in cm

11-GA50002-65-5

e

Figure 24: Benchmark model - Case3 (top view).

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Steel plate (186 x 186 x 2.5)

Air

Detail A

Water

Bottom grid A 324 x 24 x 0.4

G

Bottom grid0.41.18

7.32

Detail A

186

140

97.5*

30.25

0.98

e: separation between arraysH: height of the screenH : water critical heightc

U rodO2

189.7

Pedestal2.5

Drawing not to scaleDimensions in cm

11-GA50002-65-6

e

Hc

Top grid AG3 24 x 24 x 0.4

Fue

l col

umn

heig

ht 8

9.76

5

* Distance from top of bottom grid to bottom of top grid

Figure 25: Benchmark model - Case 4 (lateral view).

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Water or air

189.7

e: separation between arrays: 1 cmArray size: 9 x 8Total number of fuel rods: 288

189.7

Drawing not to scaleDimensions in cm

11-GA50002-65-7

e

Figure 26: Benchmark model - Case 4 (top view).

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24

24

0.4

Dimensions in cm11-GA50002-64

D 0.98

Pitch1.6

Pitch1.6

Figure 27: Upper and lower grids.

Please note: Grid regions not occupied by fuel rods that are outside the four arrays are represented as homogeneous regions of aluminum and water for the lower grid and aluminum and air for the upper grid (see Table 45 for homogeneous compositions).

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3.3 Material Data

3.3.1 Fuel Rod Materials

Fuel rod material data are derived from Table 7 through Table 12. Atom densities for these materials are given in Table 44.

Table 44: Atom densities for fuel rod materials.

Material Elements and

Isotopes Atom densities (atom/barn-cm)

O 4.6311E-02

Fe 9.5121E-06

Si 2.2475E-05

Al 4.1693E-06

234U 7.1087E-06 235U 1.1104E-03 236U 3.1792E-05

UO2

238U 2.2006E-02

N 8.7300E-06

O 3.3727E-04

Sn 4.5389E-04

Fe 1.5680E-04

Cr 8.9516E-05

C 4.2233E-05

Si 1.3904E-05

Al 2.8361E-06

Zr 4.2428E-02

Hf 1.2287E-06

Zircaloy-4 (Fuel-rod Clad, End Plugs)

H 1.4480E-05

3.3.2 Structural Materials

Structural materials data are derived from Table 13 and Table 18. They are reported in Table 45.

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Table 45: Atom densities for structural materials.

Material Elements

and Isotopes Atom densities (atom/barn-cm)

Si 2.2900E-04 Fe 1.1516E-04 Cu 2.5303E-05 Mn 1.4634E-04 Mg 2.0508E-03 Cr 9.2771E-05 Zn 4.9179E-05 Ti 5.0373E-05

AG3 Aluminum Alloy

(Grids, Top and Bottom Plate of

Baskets)

Al 5.6226E-02 Cr 1.6469E-02 Ni 8.1061E-03 Mn 8.6597E-04 Si 1.6939E-03 P 6.1438E-05 S 4.4504E-05 C 1.1883E-04

Stainless Steel Z2CN18-10

(Steel Plate of Pedestal)

Fe 5.9546E-02

O 3.3361E-02 Water

H 6.6722E-02

N 4.1985E-05 Air (a)

O 1.1263E-05

Compound Elements Atom densities (atom/barn-cm) Elements Atom densities

(atom/barn-cm) Si 1.6145E-04 Si 1.6145E-04 Fe 8.1191E-05 Fe 8.1191E-05 Cu 1.7839E-05 Cu 1.7839E-05 Mn 1.0317E-04 Mn 1.0317E-04 Mg 1.6790E-03 Mg 1.6790E-03 Cr 6.5403E-05 Cr 6.5403E-05 Zn 3.5463E-05 Zn 3.5463E-05 Ti 3.5513E-05 Ti 3.5513E-05 Al 3.9639E-02 Al 3.9639E-02 H 1.9682E-02 N 1.2386E-05

AG3 Aluminum Alloy + Water or

Air (Lower Grids and

Upper Grids without rods)

Grid +

Water

O 9.8411E-03

Grid +

Air

O 3.3226E-06

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3.3.3 Titanium Screens The screen composition is provided in Table 46.

Table 46: The atom densities for titanium screens.

Atom densities (atom/barn-cm)

4A-Ti-005 4A-Ti-010 Element

Case 1 Case 2

Fe 5.8113E-05 6.8008E-05 Cr 1.2483E-05 1.2522E-05 Ti 5.6266E-02 5.6443E-02 Sn 4.1009E-07 7.7701E-07 C 3.6027E-05 2.9363E-05 N 3.8618E-06 3.2927E-06 O 3.2117E-04 2.7130E-04 Al 1.5035E-06 5.1279E-06 Si 1.0593E-05 1.2557E-05 P 8.1204E-07 1.6642E-06

Mn 1.3784E-06 2.4691E-06 Ni 5.0690E-06 4.6224E-06

3.4 Temperature Data

The temperature of the benchmark models is 21ºC. 3.5 Experimental and Benchmark-Model keff

The critical heights reported in Table 1 are the results of measurements extrapolated to criticality. The critical heights reported are intended to correspond to an experimental keff of 1.00000.

No significant bias or additional bias uncertainty due to the simplication of the experimental device has been determined.

An analysis of experimental uncertainties was performed in Section 2.2. The benchmark keff’s for both benchmark configurations is given in Table 47.

Table 47: Benchmark keff and 1σ uncertainty.

Experiment ID Case

Experiment keff

Benchmark keff

Bias (pcm)

Bias uncertainty

(pcm)

1σσσσ uncertainty

3034 1 1.0000 0.99963 -37 12 0.0012

3049 2 1.0000 0.99936 -64 21 0.0011

3044 3 1.0000 1.00028 28 9 0.0012

3050 4 1.0000 0.99945 -55 18 0.0011

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4.0 RESULTS OF SAMPLE CALCULATIONS

Table 48 and Table 49 give the calculated keff’s obtained with: • The APOLLO2-MORET 4 codes with CEA93 172-group library based on JEF2.2 evaluation;

APOLLO2 calculates with the Pij method homogenized, self shielded macroscopic cross sections. These cross sections are then used in a MORET 4 3D Monte Carlo calculation.

• The continuous energy MORET 5 code (under validation) with JEF2.2 evaluation cross section. • The continuous energy MCNPX2.6 Monte Carlo code with ENDF/B-VII.0 cross section library. • The multi-group KENO-V.a code, using the 238-group ENDF/B-VI.7 cross section library.

Some zones comprising several materials have a low impact on reactivity; as a consequence, their materials could be homogenized. These zones are the followings:

• Bottom plug in water • Grid, bottom plug, and water • Clad in air corresponding to the spring zone • Grid, clad in air (for the spring zone) • Top plug in air • Grids, water • Grids, air.

A typical input listing is provided for the 4A-Ti-005 experiment (Case 1) for each code in APPENDIX A.

Table 48: Calculation results of benchmark model with codes using pointwise cross sections.

Case Experiment MCNPX2.6 ENDF/B-VII

keff ±±±± 1σσσσ

MORET 5 JEF2.2 keff ±±±± 1σσσσ

1 4A-Ti-005 1.0038 ± 0.0002 1.0035 ± 0.0003

2 4A-Ti-010 1.0023 ± 0.0002 1.0027 ± 0.0003

3 R4A-Eau-005 1.0025 ± 0.0004 1.0015 ± 0.0003

4 R4A-Eau-010 1.0004 ± 0.0004 1.0001 ± 0.0003

Table 49: Calculation results of benchmark model with multi-group codes.

Case Experiment

APOLLO2-MORET 4 JEF2.2 keff ± 1σ

172 group

KENO-V.a ENDF/B-VI.7

keff ± 1σ 238 group

1 4A-Ti-005 1.0102 ± 0.0001 0.9989 ± 0.0005

2 4A-Ti-010 1.0089 ± 0.0001 0.9980 ± 0.0005

3 R4A-Eau-005 1.0064 ± 0.0001 0.9968 ± 0.0005

4 R4A-Eau-010 1.0061 ± 0.0001 0.9955 ± 0.0002

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Calculations with APOLLO2-MORET 4 have a tendency to overestimate keffa significantly for both

configurations with and without titanium. This may be explained by the physical models (pij calculation and self-shielding options) of the calculational scheme. For configurations with titanium, an additional overestimation is observed and comes from the multi-group treatment of nuclear data.

Calculations with KENO-V.a have a tendency to underestimate keff significantly for both configurations without titanium. This is observed for all thermal configurations with low enriched uranium. It can be attributed to ENDF/B-VI.7 uranium cross sections. This underestimation no longer exists for experiments with titanium.

Calculations with MCNPX2.6 and MORET 5 show a quite good agreement with the benchmark keff.

a N. Leclaire, I. Duhamel, Y.K. Lee, C. Venard, Experimental validation of the French CRISTAL V1.0 package, NCSD 2005, Knoxville, Tennessee, September 19–22, 2005.

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5.0 REFERENCES

1. J. Piot – Appareillage B – Rapport définitif d’expériences – Programme Matériaux Interaction Réflexion Toutes Epaisseurs MIRTE Phase 1 - MIRTE 1 program.

2. J. Bonnet, D. Doutriaux, P. Grivot, G. Poullot « Laboratoire de Criticité de Valduc – Programme

1977/1994 – Crayons de Type REP U(4.738)O2 Gainés AGS - Compléments d’informations » - Note IPSN/SRSC/98.03 et note IPSN/SEC/T/ 98.424.- Revision B du 22/03/2002.

3. H. Lecoq « Analyses Physico-chimiques des Pastilles REP et Poudre MARACAS » [Translation:

« Physicochemical Analysis of REP Pellets and MARACAS Powder »] Note IPSN/SRSC/00.177/CA ML.

4. E. Girault « Appareillage B - Caracteristiques des Crayons Combustibles de Type "REP"

U(4,738%)O2 et Synthese des Etudes » - Rapport SRNC 03-238 [Translation: « PWR U(4,738%)O2 Fuel Rods Characteristics and Synthesis of Studies »] SRNC 03-238 Report.

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APPENDIX A: TYPICAL INPUT LISTINGS

A.1 APOLLO2-MORET 4 Input Listing

The calculation is run in two steps using the CRISTAL package (Version 1.2). APOLLO2 (release 2.5.5) is a 1-D multi-group cell code. It is used to determine material buckling Bm

2, kinfinite, and homogenized self shielded cross sections; it uses the CEA93.V6, 172-group library (derived from JEF2.2). MORET 4 is a 3-D multi-group Monte Carlo code. It uses self-shielded macroscopic cross sections coming from APOLLO2. The cross section library is derived from JEF2.2 evaluation. 8000 batches and 8000 neutrons per batch are simulated. The first 200 batches are skipped. A third code (or graphical user interface) called CIGALES is also used to generate the APOLLO input data. It also calculates atomic densities from chemical data. The benchmark models for 4A-Ti-005 configuration are presented in this appendix.

A.1.1 APOLLO2-MORET 4 input listing for thin thickn ess configuration (4A-Ti-005). ****************************************** * IRSN / SEC * * APOLLO2 / MORET 4 * ****************************************** * LEU-COMP-THERM-MIRTE * * MIRTE 1 Programme * * revision 0 * * experiment 3034-3037 * ****************************************** * Interacting configuration * * with thin screens * * * * 4 Arrays of UO2 rods (4.738 %) * * 10x10 pitch 1.6cm * * Critical Height : 69.905 cm * * Titanium 5 mm * * * ****************************************** * keff(exp)± 1 s = 1.00000 ± 0.00132 * ****************************************** * Writer N. LECLAIRE * * Reviewer F.X. LEDAUPHIN * * * ****************************************** DEBUT_APOLLO2 *=+=+=+=+=+=+=+=+=+=+=+=+=+=+=+=+=+=+=+=+=+=+=+=+=+ =+=+=+=+=+=+ * CIGALES version 3.2 en date du 12/09/2007 * Creation du Fichier le 13/12/2010 11:12:20 *=+=+=+=+=+=+=+=+=+=+=+=+=+=+=+=+=+=+=+=+=+=+=+=+=+ =+=+=+=+=+=+ * -=- INITIALISATION - CALCUL 1 -=- TOPT = TABLE: ; TRES = TABLE: ; TSTR = TABLE: ; TOPT.'CALCUL_CRISTAL' = 1 ; REPPROC = OUVRIR: 22 'VARIABLE' 1024 10000 'ADRESSE' 'aprocristal' ; CHARGE_APROCRISTAL = LIRE: REPPROC 'APROC' 'CHARGE_ APROCRISTAL' ; FERMER: REPPROC ; EXECUTER CHARGE_APROCRISTAL ;

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TRES TSTR TOPT = INITIALISER_CRISTAL 1 TSTR TOPT TR ES ; * -=- OPTIONS -=- * TOPT.'STCRI'.'NGROUP_FINAL' = 172 ; TOPT.'STCRI'.'ANISOTROPIE' = 'P5' ; * *================================================== ============ * APOLLO PIJ CALCUL 1 * ANISO = CONCAT: '&' TOPT.'STCRI'.'ANISOTROPIE' ; *================================================== ============ * * AIR TITRE: ' AIR ' ; CALCUL_AP2 = 1 ; WRITE: TOPT.'RESU' '*AIR CAS 1 ' ; * * -=- Description des milieux -=- *AIR nom_calc = 'MILHOM1' ; TOPT.'STCRI'.'CALCUL_INITIAL' = nom_calc ; TOPT.'STCRI'.'CALCULS_INITIAUX'.nom_calc = TABLE: ; TSTR.nom_calc = TABLE: ; * nom_mil = 'AIR' ; TOPT.'STMIL'.nom_mil = TABLE: ; TOPT.'STMIL'.nom_mil.'N14 ' = 4.19850E-05 ; TOPT.'STMIL'.nom_mil.'O16 ' = 1.12630E-05 ; TOPT.'STMIL'.nom_mil.'TEMPERATURE' = 21. ; * TRES TSTR TOPT = GENERE_MILIEUX_S 2 TSTR TOPT TRES ; * * -=- Creation de la geometrie -=- * TSTR.nom_calc.'GEO' = GEOM: &CYLI &MAIL 1 &EQD 1. &MILI TSTR.'MILREF'.nom_mil 1 ; * * -=- Creation de la bibliotheque interne -=- * TSTR.'APOLIB' = BIBINT: &EDIT 1 TSTR.'IDB' TSTR.nom _calc.'GEO' &SFIN &TP ( TEXTE TOPT.'REPBIB' ) ; * TSTR.nom_calc.'MAC' = MACROLIB: &EDIT TOPT.'STIMP'. 'MACROLIB' TSTR.'MILREF'.nom_mil &TOTA &SELF &ABSO &ENER &FISS &ENER &SNNN &TRAC &P0 &DIFF ANISO &TRAN ANISO ; * * -=- Creation de la Macrolib pour le milieu M ILHOM1 -=- * APOTRIM: &EDIT 1 TSTR.nom_calc.'MAC' ANISO &FICH 47 &NOMMIL TSTR.'MILREF'.nom_mil nom_mil ; DETRUIRE: TSTR.'APOLIB' ; *================================================== ============ * APOLLO PIJ CALCUL 2 *================================================== ============ * * STEEL TITRE: ' STEEL ' ; CALCUL_AP2 = 2 ; WRITE: TOPT.'RESU' '*STEEL CAS 2 ' ; * * -=- Description des milieux -=- *************************************************** ********* TRES TSTR TOPT = INITIALISER_CRISTAL 1 TSTR TOPT TR ES ; *STEEL nom_calc = 'MILHOM2' ; TOPT.'STCRI'.'CALCUL_INITIAL' = nom_calc ; TOPT.'STCRI'.'CALCULS_INITIAUX'.nom_calc = TABLE: ; TSTR.nom_calc = TABLE: ; * nom_mil = 'STEEL' ; TOPT.'STMIL'.nom_mil = TABLE: ;

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TOPT.'STMIL'.nom_mil.'CRNAT ' = 1.64690E-02 ; TOPT.'STMIL'.nom_mil.'NINAT ' = 8.10610E-03 ; TOPT.'STMIL'.nom_mil.'MN55 ' = 8.65970E-04 ; TOPT.'STMIL'.nom_mil.'SINAT ' = 1.69390E-03 ; TOPT.'STMIL'.nom_mil.'P31 ' = 6.14380E-05 ; TOPT.'STMIL'.nom_mil.'CNAT ' = 4.45090E-05 ; TOPT.'STMIL'.nom_mil.'FENAT ' = 1.18830E-04 ; TOPT.'STMIL'.nom_mil.'TEMPERATURE' = 21. ; * TRES TSTR TOPT = GENERE_MILIEUX_S 2 TSTR TOPT TRES ; * * -=- Creation de la geometrie -=- * TSTR.nom_calc.'GEO' = GEOM: &CYLI &MAIL 1 &EQD 1. &MILI TSTR.'MILREF'.nom_mil 1 ; * * -=- Creation de la bibliotheque interne -=- * TSTR.'APOLIB' = BIBINT: &EDIT 1 TSTR.'IDB' TSTR.nom _calc.'GEO' &SFIN &TP ( TEXTE TOPT.'REPBIB' ) ; * TSTR.nom_calc.'MAC' = MACROLIB: &EDIT TOPT.'STIMP'. 'MACROLIB' TSTR.'MILREF'.nom_mil &TOTA &SELF &ABSO &ENER &FISS &ENER &SNNN &TRAC &P0 &DIFF ANISO &TRAN ANISO ; * * -=- Creation de la Macrolib pour le milieu M ILHOM2 -=- * APOTRIM: &EDIT 1 TSTR.nom_calc.'MAC' ANISO &NOMA &FICH 47 &NOMMIL TSTR.'MILREF'.nom_mil nom_mil ; DETRUIRE: TSTR.'APOLIB' ; *================================================== ============ * APOLLO PIJ CALCUL 3 *================================================== ============ * * WATER TITRE: ' WATER ' ; CALCUL_AP2 = 3 ; WRITE: TOPT.'RESU' '*WATER CAS 3 ' ; * * -=- Description des milieux -=- *************************************************** ********* TRES TSTR TOPT = INITIALISER_CRISTAL 1 TSTR TOPT TR ES ; *WATER nom_calc = 'MILHOM3' ; TOPT.'STCRI'.'CALCUL_INITIAL' = nom_calc ; TOPT.'STCRI'.'CALCULS_INITIAUX'.nom_calc = TABLE: ; TSTR.nom_calc = TABLE: ; * nom_mil = 'WATER' ; TOPT.'STMIL'.nom_mil = TABLE: ; TOPT.'STMIL'.nom_mil.'H2O ' = 3.33609E-02 ; TOPT.'STMIL'.nom_mil.'TEMPERATURE' = 21. ; * TRES TSTR TOPT = GENERE_MILIEUX_S 2 TSTR TOPT TRES ; * * -=- Creation de la geometrie -=- * TSTR.nom_calc.'GEO' = GEOM: &CYLI &MAIL 1 &EQD 1. &MILI TSTR.'MILREF'.nom_mil 1 ; * * -=- Creation de la bibliotheque interne -=- * TSTR.'APOLIB' = BIBINT: &EDIT 1 TSTR.'IDB' TSTR.nom _calc.'GEO' &SFIN &TP ( TEXTE TOPT.'REPBIB' ) ; * TSTR.nom_calc.'MAC' = MACROLIB: &EDIT TOPT.'STIMP'. 'MACROLIB' TSTR.'MILREF'.nom_mil &TOTA &SELF &ABSO &ENER &FISS &ENER &SNNN &TRAC &P0 &DIFF ANISO &TRAN ANISO ; *

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* -=- Creation de la Macrolib pour le milieu M ILHOM3 -=- * APOTRIM: &EDIT 1 TSTR.nom_calc.'MAC' ANISO &NOMA &FICH 47 &NOMMIL TSTR.'MILREF'.nom_mil nom_mil ; DETRUIRE: TSTR.'APOLIB' ; *================================================== ============ * APOLLO PIJ CALCUL 4 *================================================== ============ * * AG3 TITRE: ' AG3 ' ; CALCUL_AP2 = 4 ; WRITE: TOPT.'RESU' '*AG3 CAS 4 ' ; * * -=- Description des milieux -=- *************************************************** ********* TRES TSTR TOPT = INITIALISER_CRISTAL 1 TSTR TOPT TR ES ; *AG3 nom_calc = 'MILHOM4' ; TOPT.'STCRI'.'CALCUL_INITIAL' = nom_calc ; TOPT.'STCRI'.'CALCULS_INITIAUX'.nom_calc = TABLE: ; TSTR.nom_calc = TABLE: ; * nom_mil = 'AG3' ; TOPT.'STMIL'.nom_mil = TABLE: ; TOPT.'STMIL'.nom_mil.'SINAT ' = 2.29001E-04 ; TOPT.'STMIL'.nom_mil.'FENAT ' = 1.15165E-04 ; TOPT.'STMIL'.nom_mil.'CUNAT ' = 2.53029E-05 ; TOPT.'STMIL'.nom_mil.'MN55 ' = 1.46338E-04 ; TOPT.'STMIL'.nom_mil.'MGNAT ' = 2.38159E-03 ; TOPT.'STMIL'.nom_mil.'CRNAT ' = 9.27707E-05 ; TOPT.'STMIL'.nom_mil.'ZN64 ' = 4.91790E-05 ; TOPT.'STMIL'.nom_mil.'TINAT ' = 5.03728E-05 ; TOPT.'STMIL'.nom_mil.'AL27 ' = 5.62257E-02 ; TOPT.'STMIL'.nom_mil.'TEMPERATURE' = 21. ; * TRES TSTR TOPT = GENERE_MILIEUX_S 2 TSTR TOPT TRES ; * * -=- Creation de la geometrie -=- * TSTR.nom_calc.'GEO' = GEOM: &CYLI &MAIL 1 &EQD 1. &MILI TSTR.'MILREF'.nom_mil 1 ; * * -=- Creation de la bibliotheque interne -=- * TSTR.'APOLIB' = BIBINT: &EDIT 1 TSTR.'IDB' TSTR.nom _calc.'GEO' &SFIN &TP ( TEXTE TOPT.'REPBIB' ) ; * TSTR.nom_calc.'MAC' = MACROLIB: &EDIT TOPT.'STIMP'. 'MACROLIB' TSTR.'MILREF'.nom_mil &TOTA &SELF &ABSO &ENER &FISS &ENER &SNNN &TRAC &P0 &DIFF ANISO &TRAN ANISO ; * * -=- Creation de la Macrolib pour le milieu M ILHOM4 -=- * APOTRIM: &EDIT 1 TSTR.nom_calc.'MAC' ANISO &NOMA &FICH 47 &NOMMIL TSTR.'MILREF'.nom_mil nom_mil ; DETRUIRE: TSTR.'APOLIB' ; *================================================== ============ * APOLLO PIJ CALCUL 5 *================================================== ============ * * AG3 + HOLES (air) TITRE: ' AG3 + HOLES (air) ' ; CALCUL_AP2 = 5 ; WRITE: TOPT.'RESU' '*AG3 + HOLES (air) CAS 5 ' ; * * -=- Description des milieux -=- *************************************************** ********* TRES TSTR TOPT = INITIALISER_CRISTAL 1 TSTR TOPT TR ES ; *AG3 + HOLES (air) nom_calc = 'MILHOM5' ;

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TOPT.'STCRI'.'CALCUL_INITIAL' = nom_calc ; TOPT.'STCRI'.'CALCULS_INITIAUX'.nom_calc = TABLE: ; TSTR.nom_calc = TABLE: ; * nom_mil = 'AG3 + HOLES (air)' ; TOPT.'STMIL'.nom_mil = TABLE: ; TOPT.'STMIL'.nom_mil.'SINAT ' = 1.61446E-04 ; TOPT.'STMIL'.nom_mil.'FENAT ' = 8.11911E-05 ; TOPT.'STMIL'.nom_mil.'CUNAT ' = 1.78386E-05 ; TOPT.'STMIL'.nom_mil.'MN55 ' = 1.03168E-04 ; TOPT.'STMIL'.nom_mil.'MGNAT ' = 1.67902E-03 ; TOPT.'STMIL'.nom_mil.'CRNAT ' = 6.54033E-05 ; TOPT.'STMIL'.nom_mil.'ZN64 ' = 3.54633E-05 ; TOPT.'STMIL'.nom_mil.'TINAT ' = 3.55129E-05 ; TOPT.'STMIL'.nom_mil.'AL27 ' = 3.96391E-02 ; TOPT.'STMIL'.nom_mil.'N14 ' = 1.23856E-05 ; TOPT.'STMIL'.nom_mil.'O16 ' = 3.32259E-06 ; TOPT.'STMIL'.nom_mil.'TEMPERATURE' = 21. ; * TRES TSTR TOPT = GENERE_MILIEUX_S 2 TSTR TOPT TRES ; * * -=- Creation de la geometrie -=- * TSTR.nom_calc.'GEO' = GEOM: &CYLI &MAIL 1 &EQD 1. &MILI TSTR.'MILREF'.nom_mil 1 ; * * -=- Creation de la bibliotheque interne -=- * TSTR.'APOLIB' = BIBINT: &EDIT 1 TSTR.'IDB' TSTR.nom _calc.'GEO' &SFIN &TP ( TEXTE TOPT.'REPBIB' ) ; * TSTR.nom_calc.'MAC' = MACROLIB: &EDIT TOPT.'STIMP'. 'MACROLIB' TSTR.'MILREF'.nom_mil &TOTA &SELF &ABSO &ENER &FISS &ENER &SNNN &TRAC &P0 &DIFF ANISO &TRAN ANISO ; * * -=- Creation de la Macrolib pour le milieu M ILHOM5 -=- * APOTRIM: &EDIT 1 TSTR.nom_calc.'MAC' ANISO &NOMA &FICH 47 &NOMMIL TSTR.'MILREF'.nom_mil nom_mil ; DETRUIRE: TSTR.'APOLIB' ; *================================================== ============ * APOLLO PIJ CALCUL 6 *================================================== ============ * * Titanium TITRE: ' Titanium ' ; CALCUL_AP2 = 6 ; WRITE: TOPT.'RESU' '*Titanium CAS 6 ' ; * * -=- Description des milieux -=- *************************************************** ********* TRES TSTR TOPT = INITIALISER_CRISTAL 1 TSTR TOPT TR ES ; *Titanium nom_calc = 'MILHOM6' ; TOPT.'STCRI'.'CALCUL_INITIAL' = nom_calc ; TOPT.'STCRI'.'CALCULS_INITIAUX'.nom_calc = TABLE: ; TSTR.nom_calc = TABLE: ; * nom_mil = 'Titanium' ; TOPT.'STMIL'.nom_mil = TABLE: ; TOPT.'STMIL'.nom_mil.'FENAT ' = 5.81129E-05 ; TOPT.'STMIL'.nom_mil.'CRNAT ' = 1.24834E-05 ; TOPT.'STMIL'.nom_mil.'TINAT ' = 5.62658E-02 ; TOPT.'STMIL'.nom_mil.'SNNAT ' = 4.10087E-07 ; TOPT.'STMIL'.nom_mil.'CNAT ' = 3.60273E-05 ; TOPT.'STMIL'.nom_mil.'N14 ' = 3.86176E-06 ; TOPT.'STMIL'.nom_mil.'O16 ' = 3.21174E-04 ; TOPT.'STMIL'.nom_mil.'AL27 ' = 1.50354E-06 ; TOPT.'STMIL'.nom_mil.'SINAT ' = 1.05926E-05 ; TOPT.'STMIL'.nom_mil.'P31 ' = 8.12044E-07 ; TOPT.'STMIL'.nom_mil.'MN55 ' = 1.37840E-06 ;

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TOPT.'STMIL'.nom_mil.'NINAT ' = 5.06897E-06 ; TOPT.'STMIL'.nom_mil.'TEMPERATURE' = 21. ; * TRES TSTR TOPT = GENERE_MILIEUX_S 2 TSTR TOPT TRES ; * * -=- Creation de la geometrie -=- * TSTR.nom_calc.'GEO' = GEOM: &CYLI &MAIL 1 &EQD 1. &MILI TSTR.'MILREF'.nom_mil 1 ; * * -=- Creation de la bibliotheque interne -=- * TSTR.'APOLIB' = BIBINT: &EDIT 1 TSTR.'IDB' TSTR.nom _calc.'GEO' &SFIN &TP ( TEXTE TOPT.'REPBIB' ) ; * TSTR.nom_calc.'MAC' = MACROLIB: &EDIT TOPT.'STIMP'. 'MACROLIB' TSTR.'MILREF'.nom_mil &TOTA &SELF &ABSO &ENER &FISS &ENER &SNNN &TRAC &P0 &DIFF ANISO &TRAN ANISO ; * * -=- Creation de la Macrolib pour le milieu M ILHOM6 -=- * APOTRIM: &EDIT 1 TSTR.nom_calc.'MAC' ANISO &NOMA &FICH 47 &NOMMIL TSTR.'MILREF'.nom_mil nom_mil ; DETRUIRE: TSTR.'APOLIB' ; *================================================== ============ * APOLLO PIJ CALCUL 7 *================================================== ============ * * AP TITRE: ' AP ' ; CALCUL_AP2 = 7 ; WRITE: TOPT.'RESU' '*AP CAS 7 ' ; * * -=- Description des milieux -=- *************************************************** ********* TRES TSTR TOPT = INITIALISER_CRISTAL 1 TSTR TOPT TR ES ; *AP nom_calc = 'MILHOM7' ; TOPT.'STCRI'.'CALCUL_INITIAL' = nom_calc ; TOPT.'STCRI'.'CALCULS_INITIAUX'.nom_calc = TABLE: ; TSTR.nom_calc = TABLE: ; * nom_mil = 'AP' ; TOPT.'STMIL'.nom_mil = TABLE: ; TOPT.'STMIL'.nom_mil.'N14 ' = 3.26736E-05 ; TOPT.'STMIL'.nom_mil.'O16 ' = 1.02544E-04 ; TOPT.'STMIL'.nom_mil.'SNNAT ' = 1.27090E-04 ; TOPT.'STMIL'.nom_mil.'FENAT ' = 4.39037E-05 ; TOPT.'STMIL'.nom_mil.'CRNAT ' = 2.50645E-05 ; TOPT.'STMIL'.nom_mil.'CNAT ' = 1.18252E-05 ; TOPT.'STMIL'.nom_mil.'SINAT ' = 3.89315E-06 ; TOPT.'STMIL'.nom_mil.'ZRNAT ' = 1.18798E-02 ; TOPT.'STMIL'.nom_mil.'AL27 ' = 7.94114E-07 ; TOPT.'STMIL'.nom_mil.'HFNAT ' = 3.44039E-07 ; TOPT.'STMIL'.nom_mil.'H1 ' = 4.05429E-06 ; TOPT.'STMIL'.nom_mil.'TEMPERATURE' = 21. ; * TRES TSTR TOPT = GENERE_MILIEUX_S 2 TSTR TOPT TRES ; * * -=- Creation de la geometrie -=- * TSTR.nom_calc.'GEO' = GEOM: &CYLI &MAIL 1 &EQD 1. &MILI TSTR.'MILREF'.nom_mil 1 ; * * -=- Creation de la bibliotheque interne -=- * TSTR.'APOLIB' = BIBINT: &EDIT 1 TSTR.'IDB' TSTR.nom _calc.'GEO' &SFIN &TP ( TEXTE TOPT.'REPBIB' ) ; * TSTR.nom_calc.'MAC' = MACROLIB: &EDIT TOPT.'STIMP'. 'MACROLIB'

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TSTR.'MILREF'.nom_mil &TOTA &SELF &ABSO &ENER &FISS &ENER &SNNN &TRAC &P0 &DIFF ANISO &TRAN ANISO ; * * -=- Creation de la Macrolib pour le milieu M ILHOM7 -=- * APOTRIM: &EDIT 1 TSTR.nom_calc.'MAC' ANISO &NOMA &FICH 47 &NOMMIL TSTR.'MILREF'.nom_mil nom_mil ; DETRUIRE: TSTR.'APOLIB' ; *================================================== ============ * APOLLO PIJ CALCUL 8 *================================================== ============ * * AC TITRE: ' AC ' ; CALCUL_AP2 = 8 ; WRITE: TOPT.'RESU' '*AC CAS 8 ' ; * * -=- Description des milieux -=- *************************************************** ********* TRES TSTR TOPT = INITIALISER_CRISTAL 1 TSTR TOPT TR ES ; *milieu_23 nom_calc = 'MILHOM8' ; TOPT.'STCRI'.'CALCUL_INITIAL' = nom_calc ; TOPT.'STCRI'.'CALCULS_INITIAUX'.nom_calc = TABLE: ; TSTR.nom_calc = TABLE: ; * nom_mil = 'milieu_23' ; TOPT.'STMIL'.nom_mil = TABLE: ; TOPT.'STMIL'.nom_mil.'CRNAT ' = 5.55223E-06 ; TOPT.'STMIL'.nom_mil.'H1 ' = 8.98097E-07 ; TOPT.'STMIL'.nom_mil.'HFNAT ' = 7.62107E-08 ; TOPT.'STMIL'.nom_mil.'O16 ' = 3.14833E-05 ; TOPT.'STMIL'.nom_mil.'SINAT ' = 8.62402E-07 ; TOPT.'STMIL'.nom_mil.'FENAT ' = 9.72546E-06 ; TOPT.'STMIL'.nom_mil.'N14 ' = 3.99224E-05 ; TOPT.'STMIL'.nom_mil.'CNAT ' = 2.61950E-06 ; TOPT.'STMIL'.nom_mil.'ZRNAT ' = 2.63160E-03 ; TOPT.'STMIL'.nom_mil.'AL27 ' = 1.75910E-07 ; TOPT.'STMIL'.nom_mil.'SNNAT ' = 2.81527E-05 ; TOPT.'STMIL'.nom_mil.'TEMPERATURE' = 21. ; * TRES TSTR TOPT = GENERE_MILIEUX_S 2 TSTR TOPT TRES ; * * -=- Creation de la geometrie -=- * TSTR.nom_calc.'GEO' = GEOM: &CYLI &MAIL 1 &EQD 1. &MILI TSTR.'MILREF'.nom_mil 1 ; * * -=- Creation de la bibliotheque interne -=- * TSTR.'APOLIB' = BIBINT: &EDIT 1 TSTR.'IDB' TSTR.nom _calc.'GEO' &SFIN &TP ( TEXTE TOPT.'REPBIB' ) ; * TSTR.nom_calc.'MAC' = MACROLIB: &EDIT TOPT.'STIMP'. 'MACROLIB' TSTR.'MILREF'.nom_mil &TOTA &SELF &ABSO &ENER &FISS &ENER &SNNN &TRAC &P0 &DIFF ANISO &TRAN ANISO ; * * -=- Creation de la Macrolib pour le milieu M ILHOM8 -=- * APOTRIM: &EDIT 1 TSTR.nom_calc.'MAC' ANISO &NOMA &FICH 47 &NOMMIL TSTR.'MILREF'.nom_mil nom_mil ; DETRUIRE: TSTR.'APOLIB' ; *================================================== ============ * APOLLO PIJ CALCUL 9 *================================================== ============ * * TITRE: ' ' ; CALCUL_AP2 = 9 ; WRITE: TOPT.'RESU' '( CAS 9 ' ;

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* * -=- Description des milieux -=- *************************************************** ********* TRES TSTR TOPT = INITIALISER_CRISTAL 1 TSTR TOPT TR ES ; *milieu_24 nom_calc = 'MILHOM9' ; TOPT.'STCRI'.'CALCUL_INITIAL' = nom_calc ; TOPT.'STCRI'.'CALCULS_INITIAUX'.nom_calc = TABLE: ; TSTR.nom_calc = TABLE: ; * nom_mil = 'milieu_24' ; TOPT.'STMIL'.nom_mil = TABLE: ; TOPT.'STMIL'.nom_mil.'SINAT ' = 1.62389E-04 ; TOPT.'STMIL'.nom_mil.'FENAT ' = 9.09574E-05 ; TOPT.'STMIL'.nom_mil.'CUNAT ' = 1.78475E-05 ; TOPT.'STMIL'.nom_mil.'MN55 ' = 1.03220E-04 ; TOPT.'STMIL'.nom_mil.'MGNAT ' = 1.67986E-03 ; TOPT.'STMIL'.nom_mil.'CRNAT ' = 7.09883E-05 ; TOPT.'STMIL'.nom_mil.'ZN64 ' = 3.54811E-05 ; TOPT.'STMIL'.nom_mil.'TINAT ' = 3.55306E-05 ; TOPT.'STMIL'.nom_mil.'AL27 ' = 3.96591E-02 ; TOPT.'STMIL'.nom_mil.'N14 ' = 1.03081E-05 ; TOPT.'STMIL'.nom_mil.'O16 ' = 2.35389E-05 ; TOPT.'STMIL'.nom_mil.'H1 ' = 8.98097E-07 ; TOPT.'STMIL'.nom_mil.'HFNAT ' = 7.62107E-08 ; TOPT.'STMIL'.nom_mil.'CNAT ' = 2.61950E-06 ; TOPT.'STMIL'.nom_mil.'ZRNAT ' = 2.63160E-03 ; TOPT.'STMIL'.nom_mil.'SNNAT ' = 2.81527E-05 ; TOPT.'STMIL'.nom_mil.'TEMPERATURE' = 21. ; * TRES TSTR TOPT = GENERE_MILIEUX_S 2 TSTR TOPT TRES ; * * -=- Creation de la geometrie -=- * TSTR.nom_calc.'GEO' = GEOM: &CYLI &MAIL 1 &EQD 1. &MILI TSTR.'MILREF'.nom_mil 1 ; * * -=- Creation de la bibliotheque interne -=- * TSTR.'APOLIB' = BIBINT: &EDIT 1 TSTR.'IDB' TSTR.nom _calc.'GEO' &SFIN &TP ( TEXTE TOPT.'REPBIB' ) ; * TSTR.nom_calc.'MAC' = MACROLIB: &EDIT TOPT.'STIMP'. 'MACROLIB' TSTR.'MILREF'.nom_mil &TOTA &SELF &ABSO &ENER &FISS &ENER &SNNN &TRAC &P0 &DIFF ANISO &TRAN ANISO ; * * -=- Creation de la Macrolib pour le milieu M ILHOM9 -=- * APOTRIM: &EDIT 1 TSTR.nom_calc.'MAC' ANISO &NOMA &FICH 47 &NOMMIL TSTR.'MILREF'.nom_mil nom_mil ; DETRUIRE: TSTR.'APOLIB' ; *================================================== ============ * APOLLO PIJ CALCUL 10 *================================================== ============ * *Array in air CAS 10 TITRE: 'Array in air CAS 10 ' ; CALCUL_AP2 = 10 ; WRITE: TOPT.'RESU' 'UO2 poudre ' ' CAS 10' ; * * -=- Description des milieux -=- *************************************************** ******************* TRES TSTR TOPT = INITIALISER_CRISTAL 1 TSTR TOPT TR ES ; 'CELLUL10 NZ=4 C1=.394595 C2=.418 C3=.474623 C4=.90 2703 ' ' ' ; nom_calc = 'CELLUL10' ; TOPT.'STCRI'.'CALCUL_INITIAL' = nom_calc ; TOPT.'STCRI'.'CALCULS_INITIAUX'.nom_calc = TABLE: ; TSTR.nom_calc = TABLE: ; *

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*UO2 poudre nom_mil = 'FISSIL1_ 1' ; TOPT.'STMIL'.nom_mil = TABLE: ; TOPT.'STMIL'.nom_mil.'U234 ' = 7.10870E-06 ; TOPT.'STMIL'.nom_mil.'U235 ' = 1.11040E-03 ; TOPT.'STMIL'.nom_mil.'U236 ' = 3.17920E-05 ; TOPT.'STMIL'.nom_mil.'U238 ' = 2.20060E-02 ; TOPT.'STMIL'.nom_mil.'O16 ' = 4.63210E-02 ; TOPT.'STMIL'.nom_mil.'AL27 ' = 4.16930E-06 ; TOPT.'STMIL'.nom_mil.'FENAT ' = 9.51210E-06 ; TOPT.'STMIL'.nom_mil.'SINAT ' = 2.24750E-05 ; TOPT.'STMIL'.nom_mil.'TEMPERATURE' = 21. ; * TOPT.'STMIL'.'FISSIL1_ 2' = TOPT.'STMIL'.'FISSIL1_ 1' ; TOPT.'STMIL'.'FISSIL1_ 3' = TOPT.'STMIL'.'FISSIL1_ 1' ; TOPT.'STMIL'.'FISSIL1_ 4' = TOPT.'STMIL'.'FISSIL1_ 1' ; *AIR nom_mil = 'STRUCT1 ' ; TOPT.'STMIL'.nom_mil = TABLE: ; TOPT.'STMIL'.nom_mil.'O16 ' = 1.12630E-05 ; TOPT.'STMIL'.nom_mil.'N14 ' = 4.19850E-05 ; TOPT.'STMIL'.nom_mil.'TEMPERATURE' = 21. ; * * ZR4_1_87 nom_mil = 'STRUCT2 ' ; TOPT.'STMIL'.nom_mil = TABLE: ; TOPT.'STMIL'.nom_mil.'O16 ' = 3.37265E-04 ; TOPT.'STMIL'.nom_mil.'AL27 ' = 2.83612E-06 ; TOPT.'STMIL'.nom_mil.'FENAT ' = 1.56799E-04 ; TOPT.'STMIL'.nom_mil.'SINAT ' = 1.39041E-05 ; TOPT.'STMIL'.nom_mil.'N14 ' = 8.73002E-06 ; TOPT.'STMIL'.nom_mil.'SNNAT ' = 4.53892E-04 ; TOPT.'STMIL'.nom_mil.'CRNAT ' = 8.95160E-05 ; TOPT.'STMIL'.nom_mil.'CNAT ' = 4.22329E-05 ; TOPT.'STMIL'.nom_mil.'ZRNAT ' = 4.24280E-02 ; TOPT.'STMIL'.nom_mil.'HFNAT ' = 1.22871E-06 ; TOPT.'STMIL'.nom_mil.'H1 ' = 1.44796E-05 ; TOPT.'STMIL'.nom_mil.'TEMPERATURE' = 21. ; * *AIR nom_mil = 'STRUCT3 ' ; TOPT.'STMIL'.nom_mil = TABLE: ; TOPT.'STMIL'.nom_mil.'O16 ' = 1.12630E-05 ; TOPT.'STMIL'.nom_mil.'N14 ' = 4.19850E-05 ; TOPT.'STMIL'.nom_mil.'TEMPERATURE' = 21. ; * TRES TSTR TOPT = GENERE_MILIEUX_S 2 TSTR TOPT TRES ; * * -=- Creation de la geometrie -=- * TSTR.nom_calc.'GEO' = GEOM: &CYLI &MAIL 4 .279021 .352936 .384604 .394595 1 &EQD .418 1 &EQD .474623 4 &EQD .902703 &MILI TSTR.'MILREF'.'FISSIL1_ 1' 1 TSTR.'MILREF'.'FISSIL1_ 2' 2 TSTR.'MILREF'.'FISSIL1_ 3' 3 TSTR.'MILREF'.'FISSIL1_ 4' 4 TSTR.'MILREF'.'STRUCT1 ' 5 TSTR.'MILREF'.'STRUCT2 ' 6 TSTR.'MILREF'.'STRUCT3 ' 7 &A 10 ; * * -=- Creation de la bibliotheque interne -=- * TSTR.'APOLIB' = BIBINT: &EDIT 1 TSTR.'IDB' TSTR.nom _calc.'GEO' &SFIN &TP ( TEXTE TOPT.'REPBIB' ) ; * * -=- Autoprotection -=-

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* TSTR.'GEOAU' = TSTR.nom_calc.'GEO' ; TRES TSTR TOPT = AUTOPROTECTION_CRI_S 1 TSTR TOPT T RES ; * * -=- Flux a B2 nul -=- * TOPT.'TYPE_B2' = 'NUL' ; TOPT.'STPIJ' = TABLE: ; TOPT.'STPIJ'.'UP' = 'LINEAIRE' ; TRES TSTR TOPT = CALFLUX_PIJ_CRI_S 1 TSTR TOPT TRES ; * * -=- Flux a B2 critique -=- * SI ( TRES.'KINF' GT 1. ) ; TOPT.'TYPE_B2' = 'CRITIQUE' ; TRES TSTR TOPT = CALFLUX_PIJ_CRI_S 1 TSTR TOPT TRES ; FINSI ; * TOPT.'STCRI'.'CALCULS_INITIAUX'.nom_calc.'B2' = TRE S.'B2' ; TOPT.'STCRI'.'CALCULS_INITIAUX'.nom_calc.'KINF' = T RES.'KINF' ; * * -=- Sorties CARA Etendues -=- * TRES TSTR TOPT = SORTIE_FCARA_S 1 TSTR TOPT TRES ; * * -=- Condensation homogeneisation -=- * TRES TSTR TOPT = HOMOGE_COND_S 1 TSTR TOPT TRES ; * * -=- Creation de la Macrolib pour CELLUL10 -= - * APOTRIM: &EDIT 1 TSTR.nom_calc.'MAC' TOPT.'STCRI'.' ANISOTROPIE' &NOMA &FICH 47 &NOMMIL TSTR.nom_calc.'MILEQ' no m_calc ; DETRUIRE: TSTR.'APOLIB' ; *================================================== ============ * APOLLO PIJ CALCUL 11 *================================================== ============ * *Array in water CAS 11 TITRE: 'Array in water CAS 11 ' ; CALCUL_AP2 = 11 ; WRITE: TOPT.'RESU' 'UO2 poudre ' ' CAS 11' ; * * -=- Description des milieux -=- *************************************************** ******************* TRES TSTR TOPT = INITIALISER_CRISTAL 1 TSTR TOPT TR ES ; 'CELLUL11 NZ=4 C1=.394595 C2=.418 C3=.474623 C4=.90 2703 ' ' ' ; nom_calc = 'CELLUL11' ; TOPT.'STCRI'.'CALCUL_INITIAL' = nom_calc ; TOPT.'STCRI'.'CALCULS_INITIAUX'.nom_calc = TABLE: ; TSTR.nom_calc = TABLE: ; * *UO2 poudre nom_mil = 'FISSIL1_ 1' ; TOPT.'STMIL'.nom_mil = TABLE: ; TOPT.'STMIL'.nom_mil.'U234 ' = 7.10870E-06 ; TOPT.'STMIL'.nom_mil.'U235 ' = 1.11040E-03 ; TOPT.'STMIL'.nom_mil.'U236 ' = 3.17920E-05 ; TOPT.'STMIL'.nom_mil.'U238 ' = 2.20060E-02 ; TOPT.'STMIL'.nom_mil.'O16 ' = 4.63210E-02 ; TOPT.'STMIL'.nom_mil.'AL27 ' = 4.16930E-06 ; TOPT.'STMIL'.nom_mil.'FENAT ' = 9.51210E-06 ; TOPT.'STMIL'.nom_mil.'SINAT ' = 2.24750E-05 ; TOPT.'STMIL'.nom_mil.'TEMPERATURE' = 21. ; * TOPT.'STMIL'.'FISSIL1_ 2' = TOPT.'STMIL'.'FISSIL1_ 1' ; TOPT.'STMIL'.'FISSIL1_ 3' = TOPT.'STMIL'.'FISSIL1_ 1' ; TOPT.'STMIL'.'FISSIL1_ 4' = TOPT.'STMIL'.'FISSIL1_ 1' ; *AIR nom_mil = 'STRUCT1 ' ; TOPT.'STMIL'.nom_mil = TABLE: ;

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TOPT.'STMIL'.nom_mil.'O16 ' = 1.12630E-05 ; TOPT.'STMIL'.nom_mil.'N14 ' = 4.19850E-05 ; TOPT.'STMIL'.nom_mil.'TEMPERATURE' = 21. ; * * ZR4_1_87 nom_mil = 'STRUCT2 ' ; TOPT.'STMIL'.nom_mil = TABLE: ; TOPT.'STMIL'.nom_mil.'O16 ' = 3.37265E-04 ; TOPT.'STMIL'.nom_mil.'AL27 ' = 2.83612E-06 ; TOPT.'STMIL'.nom_mil.'FENAT ' = 1.56799E-04 ; TOPT.'STMIL'.nom_mil.'SINAT ' = 1.39041E-05 ; TOPT.'STMIL'.nom_mil.'N14 ' = 8.73002E-06 ; TOPT.'STMIL'.nom_mil.'SNNAT ' = 4.53892E-04 ; TOPT.'STMIL'.nom_mil.'CRNAT ' = 8.95160E-05 ; TOPT.'STMIL'.nom_mil.'CNAT ' = 4.22329E-05 ; TOPT.'STMIL'.nom_mil.'ZRNAT ' = 4.24280E-02 ; TOPT.'STMIL'.nom_mil.'HFNAT ' = 1.22871E-06 ; TOPT.'STMIL'.nom_mil.'H1 ' = 1.44796E-05 ; TOPT.'STMIL'.nom_mil.'TEMPERATURE' = 21. ; * *EAU a 21 degres nom_mil = 'STRUCT3 ' ; TOPT.'STMIL'.nom_mil = TABLE: ; TOPT.'STMIL'.nom_mil.'H2O ' = 3.33597E-02 ; TOPT.'STMIL'.nom_mil.'TEMPERATURE' = 21. ; * TRES TSTR TOPT = GENERE_MILIEUX_S 2 TSTR TOPT TRES ; * * -=- Creation de la geometrie -=- * TSTR.nom_calc.'GEO' = GEOM: &CYLI &MAIL 4 .279021 .352936 .384604 .394595 1 &EQD .418 1 &EQD .474623 4 &EQD .902703 &MILI TSTR.'MILREF'.'FISSIL1_ 1' 1 TSTR.'MILREF'.'FISSIL1_ 2' 2 TSTR.'MILREF'.'FISSIL1_ 3' 3 TSTR.'MILREF'.'FISSIL1_ 4' 4 TSTR.'MILREF'.'STRUCT1 ' 5 TSTR.'MILREF'.'STRUCT2 ' 6 TSTR.'MILREF'.'STRUCT3 ' 7 &A 10 ; * * -=- Creation de la bibliotheque interne -=- * TSTR.'APOLIB' = BIBINT: &EDIT 1 TSTR.'IDB' TSTR.nom _calc.'GEO' &SFIN &TP ( TEXTE TOPT.'REPBIB' ) ; * * -=- Autoprotection -=- * TSTR.'GEOAU' = TSTR.nom_calc.'GEO' ; TRES TSTR TOPT = AUTOPROTECTION_CRI_S 1 TSTR TOPT T RES ; * * -=- Flux a B2 nul -=- * TOPT.'TYPE_B2' = 'NUL' ; TOPT.'STPIJ' = TABLE: ; TOPT.'STPIJ'.'UP' = 'LINEAIRE' ; TRES TSTR TOPT = CALFLUX_PIJ_CRI_S 1 TSTR TOPT TRES ; * * -=- Flux a B2 critique -=- * SI ( TRES.'KINF' GT 1. ) ; TOPT.'TYPE_B2' = 'CRITIQUE' ; TRES TSTR TOPT = CALFLUX_PIJ_CRI_S 1 TSTR TOPT TRES ; FINSI ; * TOPT.'STCRI'.'CALCULS_INITIAUX'.nom_calc.'B2' = TRE S.'B2' ; TOPT.'STCRI'.'CALCULS_INITIAUX'.nom_calc.'KINF' = T RES.'KINF' ;

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* * -=- Sorties CARA Etendues -=- * TRES TSTR TOPT = SORTIE_FCARA_S 1 TSTR TOPT TRES ; * * -=- Condensation homogeneisation -=- * TRES TSTR TOPT = HOMOGE_COND_S 1 TSTR TOPT TRES ; * * -=- Creation de la Macrolib pour CELLUL11 -= - * APOTRIM: &EDIT 1 TSTR.nom_calc.'MAC' TOPT.'STCRI'.' ANISOTROPIE' &NOMA &FICH 47 &NOMMIL TSTR.nom_calc.'MILEQ' no m_calc ; DETRUIRE: TSTR.'APOLIB' ; *================================================== ============ * APOLLO PIJ CALCUL 12 *================================================== ============ * * WP TITRE: ' WP ' ; CALCUL_AP2 = 12 ; WRITE: TOPT.'RESU' '*WP CAS 12 ' ; * * -=- Description des milieux -=- *************************************************** ********* TRES TSTR TOPT = INITIALISER_CRISTAL 1 TSTR TOPT TR ES ; *WP nom_calc = 'MILHOM10' ; TOPT.'STCRI'.'CALCUL_INITIAL' = nom_calc ; TOPT.'STCRI'.'CALCULS_INITIAUX'.nom_calc = TABLE: ; TSTR.nom_calc = TABLE: ; * nom_mil = 'WP' ; TOPT.'STMIL'.nom_mil = TABLE: ; TOPT.'STMIL'.nom_mil.'H2O ' = 2.40190E-02 ; TOPT.'STMIL'.nom_mil.'O16 ' = 9.44342E-05 ; TOPT.'STMIL'.nom_mil.'AL27 ' = 7.94114E-07 ; TOPT.'STMIL'.nom_mil.'FENAT ' = 4.39037E-05 ; TOPT.'STMIL'.nom_mil.'SINAT ' = 3.89315E-06 ; TOPT.'STMIL'.nom_mil.'N14 ' = 2.44440E-06 ; TOPT.'STMIL'.nom_mil.'SNNAT ' = 1.27090E-04 ; TOPT.'STMIL'.nom_mil.'CRNAT ' = 2.50645E-05 ; TOPT.'STMIL'.nom_mil.'CNAT ' = 1.18252E-05 ; TOPT.'STMIL'.nom_mil.'HFNAT ' = 3.44039E-07 ; TOPT.'STMIL'.nom_mil.'H1 ' = 4.05429E-06 ; TOPT.'STMIL'.nom_mil.'ZRNAT ' = 1.18798E-02 ; TOPT.'STMIL'.nom_mil.'TEMPERATURE' = 21. ; * TRES TSTR TOPT = GENERE_MILIEUX_S 2 TSTR TOPT TRES ; * * -=- Creation de la geometrie -=- * TSTR.nom_calc.'GEO' = GEOM: &CYLI &MAIL 1 &EQD 1. &MILI TSTR.'MILREF'.nom_mil 1 ; * * -=- Creation de la bibliotheque interne -=- * TSTR.'APOLIB' = BIBINT: &EDIT 1 TSTR.'IDB' TSTR.nom _calc.'GEO' &SFIN &TP ( TEXTE TOPT.'REPBIB' ) ; * TSTR.nom_calc.'MAC' = MACROLIB: &EDIT TOPT.'STIMP'. 'MACROLIB' TSTR.'MILREF'.nom_mil &TOTA &SELF &ABSO &ENER &FISS &ENER &SNNN &TRAC &P0 &DIFF ANISO &TRAN ANISO ; * * -=- Creation de la Macrolib pour le milieu M ILHOM10 -=- * APOTRIM: &EDIT 1 TSTR.nom_calc.'MAC' ANISO &NOMA &FICH 47 &NOMMIL TSTR.'MILREF'.nom_mil nom_mil ; DETRUIRE: TSTR.'APOLIB' ; *================================================== ============ * APOLLO PIJ CALCUL 13

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*================================================== ============ * * WPG TITRE: ' WPG ' ; CALCUL_AP2 = 13 ; WRITE: TOPT.'RESU' '*WPG CAS 13 ' ; * * -=- Description des milieux -=- *************************************************** ********* TRES TSTR TOPT = INITIALISER_CRISTAL 1 TSTR TOPT TR ES ; *WPG nom_calc = 'MILHOM11' ; TOPT.'STCRI'.'CALCUL_INITIAL' = nom_calc ; TOPT.'STCRI'.'CALCULS_INITIAUX'.nom_calc = TABLE: ; TSTR.nom_calc = TABLE: ; * nom_mil = 'WPG' ; TOPT.'STMIL'.nom_mil = TABLE: ; TOPT.'STMIL'.nom_mil.'SINAT ' = 1.65301E-04 ; TOPT.'STMIL'.nom_mil.'FENAT ' = 1.24672E-04 ; TOPT.'STMIL'.nom_mil.'CUNAT ' = 1.78386E-05 ; TOPT.'STMIL'.nom_mil.'MN55 ' = 1.03168E-04 ; TOPT.'STMIL'.nom_mil.'MGNAT ' = 1.67902E-03 ; TOPT.'STMIL'.nom_mil.'CRNAT ' = 9.02261E-05 ; TOPT.'STMIL'.nom_mil.'ZN64 ' = 3.54633E-05 ; TOPT.'STMIL'.nom_mil.'TINAT ' = 3.55129E-05 ; TOPT.'STMIL'.nom_mil.'AL27 ' = 3.96399E-02 ; TOPT.'STMIL'.nom_mil.'N14 ' = 2.42084E-06 ; TOPT.'STMIL'.nom_mil.'O16 ' = 9.35236E-05 ; TOPT.'STMIL'.nom_mil.'SNNAT ' = 1.25864E-04 ; TOPT.'STMIL'.nom_mil.'CNAT ' = 1.17112E-05 ; TOPT.'STMIL'.nom_mil.'ZRNAT ' = 1.17653E-02 ; TOPT.'STMIL'.nom_mil.'HFNAT ' = 3.40722E-07 ; TOPT.'STMIL'.nom_mil.'H1 ' = 4.01519E-06 ; TOPT.'STMIL'.nom_mil.'H2O ' = 5.90487E-04 ; TOPT.'STMIL'.nom_mil.'TEMPERATURE' = 21. ; * TRES TSTR TOPT = GENERE_MILIEUX_S 2 TSTR TOPT TRES ; * * -=- Creation de la geometrie -=- * TSTR.nom_calc.'GEO' = GEOM: &CYLI &MAIL 1 &EQD 1. &MILI TSTR.'MILREF'.nom_mil 1 ; * * -=- Creation de la bibliotheque interne -=- * TSTR.'APOLIB' = BIBINT: &EDIT 1 TSTR.'IDB' TSTR.nom _calc.'GEO' &SFIN &TP ( TEXTE TOPT.'REPBIB' ) ; * TSTR.nom_calc.'MAC' = MACROLIB: &EDIT TOPT.'STIMP'. 'MACROLIB' TSTR.'MILREF'.nom_mil &TOTA &SELF &ABSO &ENER &FISS &ENER &SNNN &TRAC &P0 &DIFF ANISO &TRAN ANISO ; * * -=- Creation de la Macrolib pour le milieu M ILHOM11 -=- * APOTRIM: &EDIT 1 TSTR.nom_calc.'MAC' ANISO &NOMA &FICH 47 &NOMMIL TSTR.'MILREF'.nom_mil nom_mil ; DETRUIRE: TSTR.'APOLIB' ; *================================================== ============ * APOLLO PIJ CALCUL 14 *================================================== ============ * * AG3 + HOLES (water) TITRE: ' AG3 + HOLES (water) ' ; CALCUL_AP2 = 14 ; WRITE: TOPT.'RESU' '*AG3 + HOLES (water) CA S 14 ' ; * * -=- Description des milieux -=- *************************************************** ********* TRES TSTR TOPT = INITIALISER_CRISTAL 1 TSTR TOPT TR ES ; *AG3 + HOLES (water)

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nom_calc = 'MILHOM12' ; TOPT.'STCRI'.'CALCUL_INITIAL' = nom_calc ; TOPT.'STCRI'.'CALCULS_INITIAUX'.nom_calc = TABLE: ; TSTR.nom_calc = TABLE: ; * nom_mil = 'AG3 + HOLES (water)' ; TOPT.'STMIL'.nom_mil = TABLE: ; TOPT.'STMIL'.nom_mil.'SINAT ' = 1.61446E-04 ; TOPT.'STMIL'.nom_mil.'FENAT ' = 8.11911E-05 ; TOPT.'STMIL'.nom_mil.'CUNAT ' = 1.78386E-05 ; TOPT.'STMIL'.nom_mil.'MN55 ' = 1.03168E-04 ; TOPT.'STMIL'.nom_mil.'MGNAT ' = 1.67902E-03 ; TOPT.'STMIL'.nom_mil.'CRNAT ' = 6.54033E-05 ; TOPT.'STMIL'.nom_mil.'ZN64 ' = 3.54633E-05 ; TOPT.'STMIL'.nom_mil.'TINAT ' = 3.55129E-05 ; TOPT.'STMIL'.nom_mil.'AL27 ' = 3.96391E-02 ; TOPT.'STMIL'.nom_mil.'H2O ' = 9.84111E-03 ; TOPT.'STMIL'.nom_mil.'TEMPERATURE' = 21. ; * TRES TSTR TOPT = GENERE_MILIEUX_S 2 TSTR TOPT TRES ; * * -=- Creation de la geometrie -=- * TSTR.nom_calc.'GEO' = GEOM: &CYLI &MAIL 1 &EQD 1. &MILI TSTR.'MILREF'.nom_mil 1 ; * * -=- Creation de la bibliotheque interne -=- * TSTR.'APOLIB' = BIBINT: &EDIT 1 TSTR.'IDB' TSTR.nom _calc.'GEO' &SFIN &TP ( TEXTE TOPT.'REPBIB' ) ; * TSTR.nom_calc.'MAC' = MACROLIB: &EDIT TOPT.'STIMP'. 'MACROLIB' TSTR.'MILREF'.nom_mil &TOTA &SELF &ABSO &ENER &FISS &ENER &SNNN &TRAC &P0 &DIFF ANISO &TRAN ANISO ; * * -=- Creation de la Macrolib pour le milieu M ILHOM12 -=- * APOTRIM: &EDIT 1 TSTR.nom_calc.'MAC' ANISO &NOMA &FICH 47 &NOMMIL TSTR.'MILREF'.nom_mil nom_mil ; DETRUIRE: TSTR.'APOLIB' ; * EDTIME: ; ARRET: ; FIN_APOLLO2 ****************************************** * IRSN / SEC * * APOLLO2 / MORET 4 * ****************************************** * LEU-COMP-THERM-MIRTE * * MIRTE 1 Programme * * revision 0 * * experiment 3034-3037 * ****************************************** * Interacting configuration * * with thin screens * * * * 4 Arrays of UO2 rods (4.738 %) * * 10x10 pitch 1.6cm * * Critical Height : 69.905 cm * * Titanium 5 mm * * * ****************************************** * keff(exp)± 1 s = 1.00000 ± 0.00132 * ****************************************** * Writer N. LECLAIRE * * Reviewer F.X. LEDAUPHIN * * * ****************************************** *=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=* =*=*=*=*=*=*=*=*=*=*=* * CIGALES version 3.1 en date du 06/04/2006 *=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=*=* =*=*=*=*=*=*=*=*=*=*=*

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( AIR *AIR * Milieu 1 macroscopique *AIR 1 ) OPTION V6 GROUP 172 P5 TEMPER 21 FINOPTION MORET GEOM HOMO CHIMIE *AIR TEMP 21 MACRO 1 1 AIR 1.00000E+00 FINC SECTION TOUT FIN ( STEEL *STEEL * Milieu 1 CONC. ATOMIQUES- %volumique 100 *CRNAT 1.64690E-02 *NINAT 8.10610E-03 *MN55 8.65970E-04 *SINAT 1.69390E-03 *P31 6.14380E-05 *S32 4.45040E-05 *CNAT 1.18830E-04 *FENAT 5.95460E-02 ) OPTION V6 GROUP 172 P5 TEMPER 21 FINOPTION MORET GEOM HOMO CHIMIE *STEEL TEMP 21 MICRO 1 8 CRNAT NINAT MN55 SINAT P31 S32 CNAT FENAT CONC 1.64690E-02 8.10610E-03 8.65970E-04 1.69390E -03 6.14380E-05 4.45040E-05 1.18830E-04 5.95460E-02 FINC SECTION TOUT FIN ( WATER *WATER * Milieu 1 macroscopique *EAU 1 ) OPTION V6 GROUP 172 P5 TEMPER 21 FINOPTION MORET GEOM HOMO CHIMIE *WATER TEMP 21 MACRO 1 1 EAU 1.00000E+00 FINC SECTION TOUT FIN ( AG3 *AG3 * Milieu 1 %-prop MASSIQUES- Dens= 2.67000007629395 - %volumique 100 *SINAT 0.004 *FENAT 0.004 *CUNAT 0.001 *MN55 0.005 *MGNAT 0.036 *CRNAT 0.003 *ZN64 0.002 *TINAT 0.0015 *AL27 0.9435

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) OPTION V6 GROUP 172 P5 TEMPER 21 FINOPTION MORET GEOM HOMO CHIMIE *AG3 TEMP 21 MICRO 1 9 SINAT FENAT CUNAT MN55 MGNAT CRNAT ZN64 TINAT AL27 CONC 2.29001E-04 1.15165E-04 2.53029E-05 1.46338 E-04 2.38159E-03 9.27707E-05 4.91790E-05 5.03728E-05 5.62257E-0 2 FINC SECTION TOUT FIN ( AG3 + HOLES (air) *AG3 + HOLES (air) * Milieu 1 %-prop MASSIQUES- Dens= 2.67000007629395 - %volumique 70.5 *SINAT 0.004 *FENAT 0.004 *CUNAT 0.001 *MN55 0.005 *MGNAT 0.036 *CRNAT 0.003 *ZN64 0.002 *TINAT 0.0015 *AL27 0.9435 * Milieu 2 CONC. ATOMIQUES- %volumique 29.5 *N14 4.1985E-05 *O16 1.1263E-05 ) OPTION V6 GROUP 172 P5 TEMPER 21 FINOPTION MORET GEOM HOMO CHIMIE *AG3 + HOLES (air) TEMP 21 MICRO 1 11 SINAT FENAT CUNAT MN55 MGNAT CRNAT ZN64 TINAT AL27 N14 O16 CONC 1.61446E-04 8.11911E-05 1.78386E-05 1.03168 E-04 1.67902E-03 6.54033E-05 3.54633E-05 3.55129E-05 3.96391E-0 2 1.23856E-05 3.32259E-06 FINC SECTION TOUT FIN ( Titanium *Titanium * Milieu 1 CONC. ATOMIQUES- %volumique 10 * FENAT 5.81129E-05 * CRNAT 1.24834E-05 * TINAT 5.62658E-02 * SNNAT 4.10087E-07 * CNAT 3.60273E-05 * N14 3.86176E-06 * O16 3.21174E-04 * AL27 1.50354E-06 * SINAT 1.05926E-05 * P31 8.12044E-07 * MN55 1.37840E-06 * NINAT 5.06897E-06 ) OPTION V6 GROUP 172 P5 TEMPER 21 FINOPTION MORET GEOM HOMO CHIMIE *Titanium TEMP 21 MICRO 1 12 FENAT CRNAT TINAT SNNAT CNAT N14 O16 AL27 SINAT P31 MN55 NINAT CONC 5.81129E-05 1.24834E-05 5.62658E-02 4.1 0087E-07 3.60273E-05 3.86176E-06 3.21174E-04 1.50354E-06 1.05926E-05 8.120 44E-07 1.37840E-06 5.06897E-06

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FINC SECTION TOUT FIN ( AP *AP * Milieu 1 CONC. ATOMIQUES- %volumique 72 *N14 4.1985E-05 *O16 1.1263E-05 * Milieu 2 CONC. ATOMIQUES- %volumique 28 *N14 8.73002E-06 *O16 3.37265E-04 *SNNAT 4.53892E-04 *FENAT 1.56799E-04 *CRNAT 8.9516E-05 *CNAT 4.22329E-05 *SINAT 1.39041E-05 *ZRNAT 4.2428E-02 *AL27 2.83612E-06 *HFNAT 1.22871E-06 *H1 1.44796E-05 ) OPTION V6 GROUP 172 P5 TEMPER 21 FINOPTION MORET GEOM HOMO CHIMIE *AP TEMP 21 MICRO 1 11 N14 O16 SNNAT FENAT CRNAT CNAT SINAT ZRNAT AL27 HFNAT H1 CONC 3.26736E-05 1.02544E-04 1.27090E-04 4.39037 E-05 2.50645E-05 1.18252E-05 3.89315E-06 1.18798E-02 7.94114E-0 7 3.44039E-07 4.05429E-06 FINC SECTION TOUT FIN ( AC *AC * Milieu 1 CONC. ATOMIQUES- %volumique 6.2025001 *CRNAT 8.9516E-05 *H1 1.44796E-05 *HFNAT 1.22871E-06 *O16 3.37265E-04 *SINAT 1.39041E-05 *FENAT 1.56799E-04 *N14 8.73002E-06 *CNAT 4.22329E-05 *ZRNAT 0.042428 *AL27 2.83612E-06 *SNNAT 4.53892E-04 * Milieu 2 CONC. ATOMIQUES- %volumique 93.7974999 *N14 4.1985E-05 *O16 1.1263E-05 ) OPTION V6 GROUP 172 P5 TEMPER 21 FINOPTION MORET GEOM HOMO CHIMIE *milieu_23 TEMP 21 MICRO 1 11 CRNAT H1 HFNAT O16 SINAT FENAT N14 CNAT ZRNAT AL27 SNNAT CONC 5.55223E-06 8.98097E-07 7.62107E-08 3.14833 E-05 8.62402E-07 9.72546E-06 3.99224E-05 2.61950E-06 2.63160E-0 3 1.75910E-07 2.81527E-05 FINC SECTION TOUT FIN (

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( ACG *ACG * Milieu 1 CONC. ATOMIQUES- %volumique 70.535297 *SINAT 2.29001E-04 *FENAT 1.15165E-04 *CUNAT 2.53029E-05 *MN55 1.46338E-04 *MGNAT 2.38159E-03 *CRNAT 9.27707E-05 *ZN64 5.03026E-05 *TINAT 5.03728E-05 *AL27 0.0562257 * Milieu 2 CONC. ATOMIQUES- %volumique 23.2622029 *N14 4.1985E-05 *O16 1.1263E-05 * Milieu 3 CONC. ATOMIQUES- %volumique 6.20250007 *CRNAT 8.9516E-05 *H1 1.44796E-05 *HFNAT 1.22871E-06 *O16 3.37265E-04 *SINAT 1.39041E-05 *FENAT 1.56799E-04 *N14 8.73002E-06 *CNAT 4.22329E-05 *ZRNAT 0.042428 *AL27 2.83612E-06 *SNNAT 4.53892E-04 ) OPTION V6 GROUP 172 P5 TEMPER 21 FINOPTION MORET GEOM HOMO CHIMIE *milieu_24 TEMP 21 MICRO 1 16 SINAT FENAT CUNAT MN55 MGNAT CRNAT ZN64 TINAT AL27 N14 O16 H1 HFNAT CNAT ZRNAT SNNAT CONC 1.62389E-04 9.09574E-05 1.78475E-05 1.03220 E-04 1.67986E-03 7.09883E-05 3.54811E-05 3.55306E-05 3.96591E-0 2 1.03081E-05 2.35389E-05 8.98097E-07 7.62107E-08 2.61950E-0 6 2.63160E-03 2.81527E-05 FINC SECTION TOUT FIN * RAPPEL DONNEES MORET Pij *================================================== ===================== * BIBLIO CEA93.V6 172 groupes ANISOTROPIE P5 *__________________________________________________ _____________________ *<*><*><*><*><*><*><*><*><*<*><*><*><*><*><*<*><*>< *><*><*><*><*><*><*><*> * * RAPPEL GEOMETRIE du MILIEU FISSILE HETEROGENE A rray in air * * * GEOMETRIE CYLINDRIQUE *__________________________________________________ _____________________ * ZONES NB POINTS ABSCISSES CHIMIE * 1 0.394595 FISS1 * 2 0.418 AIR * 3 0.4746225 AUTRE * 4 0.902703 AIR *__________________________________________________ _____________________ * MILIEU FISSILE 1: <*><*><*><*><*><*><*><*><*<*><*><*><*><*><*<*><*><* ><*><*><*><*><*><*><*> RAPPEL MILIEU AUTRE UO2 poudre Milieu 1 CONC. ATOMIQUES- %volumique 100 8 U234 7.10870E-06 U235 1.11040E-03

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U236 3.17920E-05 U238 0.022006 O16 0.0463210 AL27 4.16930E-06 FENAT 9.51210E-06 SINAT 2.24750E-05 *__________________________________________________ _____________________ *<*><*><*><*><*><*><*><*><*<*><*><*><*><*><*<*><*>< *><*><*><*><*><*><*><*> * * RAPPEL MILIEU AUTRE * *ZR4_1_87 ***** Milieu 1 CONC. ATOMIQUES- %volumique 100 *N14 8.73002E-06 *O16 3.37265E-04 *SNNAT 4.53892E-04 *FENAT 1.56799E-04 *CRNAT 8.9516E-05 *CNAT 4.22329E-05 *SINAT 1.39041E-05 *ZRNAT 0.042428 *AL27 2.83612E-06 *HFNAT 1.22871E-06 *H1 1.44796E-05 ( Array in air CAS 10 UO2 poudre § CAS 10 *UO2 poudre SORTIE SECTIONS TOUTE LA CELLULE ) OPTION V6 GROUP 172 P5 TEMPER 21 FINOPTION MORET GEOMETRIE CYLINDRE 1. 4 4 1 0.394595 1 2 0.418 1 3 0.4746225 4 4 0.902703 AUTO 1 1 CHIMIE *UO2 poudre TEMP 21 MICRO 1 8 U234 U235 U236 U238 O16 AL27 FENAT SINAT CONC 7.10870E-06 1.11040E-03 3.17920E-05 2.20 060E-02 4.63210E-02 4.16930E-06 9.51210E-06 2.24750E-05 *AIR TEMP 21 MACRO 1 1 AIR 1 * ZR4_1_87 TEMP 21 MICRO 1 11 N14 O16 SNNAT FENAT CRNAT CNAT SINAT ZRNAT AL27 HFNAT H1 CONC 8.73002E-06 3.37265E-04 4.53892E-04 1.56 799E-04 8.95160E-05 4.22329E-05 1.39041E-05 4.24280E-02 2.83612E-0 6 1.22871E-06 1.44796E-05 *AIR TEMP 21 MACRO 1 1 AIR 1 FINC SECTION TOUT FIN * RAPPEL DONNEES MORET Pij *================================================== ===================== * BIBLIO CEA93.V6 172 groupes ANISOTROPIE P5 *__________________________________________________ _____________________ *<*><*><*><*><*><*><*><*><*<*><*><*><*><*><*<*><*>< *><*><*><*><*><*><*><*> * * RAPPEL GEOMETRIE du MILIEU FISSILE HETEROGENE A rray in water * * * GEOMETRIE CYLINDRIQUE

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*__________________________________________________ _____________________ * ZONES NB POINTS ABSCISSES CHIMIE * 1 0.394595 FISS1 * 2 0.418 AIR * 3 0.4746225 AUTRE * 4 0.902703 EAU *__________________________________________________ _____________________ * MILIEU FISSILE 1: <*><*><*><*><*><*><*><*><*<*><*><*><*><*><*<*><*><* ><*><*><*><*><*><*><*> RAPPEL MILIEU AUTRE UO2 poudre Milieu 1 CONC. ATOMIQUES- %volumique 100 8 U234 7.10870E-06 U235 1.11040E-03 U236 3.17920E-05 U238 0.022006 O16 0.0463210 AL27 4.16930E-06 FENAT 9.51210E-06 SINAT 2.24750E-05 *__________________________________________________ _____________________ *<*><*><*><*><*><*><*><*><*<*><*><*><*><*><*<*><*>< *><*><*><*><*><*><*><*> * * RAPPEL MILIEU AUTRE * *ZR4_1_87 ***** Milieu 1 CONC. ATOMIQUES- %volumique 100 *N14 8.73002E-06 *O16 3.37265E-04 *SNNAT 4.53892E-04 *FENAT 1.56799E-04 *CRNAT 8.9516E-05 *CNAT 4.22329E-05 *SINAT 1.39041E-05 *ZRNAT 0.042428 *AL27 2.83612E-06 *HFNAT 1.22871E-06 *H1 1.44796E-05 ( Array in water CAS 11 UO2 poudre § CAS 11 *UO2 poudre SORTIE SECTIONS TOUTE LA CELLULE ) OPTION V6 GROUP 172 P5 TEMPER 21 FINOPTION MORET GEOMETRIE CYLINDRE 1. 4 4 1 0.394595 1 2 0.418 1 3 0.4746225 4 4 0.902703 AUTO 1 1 CHIMIE *UO2 poudre TEMP 21 MICRO 1 8 U234 U235 U236 U238 O16 AL27 FENAT SINAT CONC 7.10870E-06 1.11040E-03 3.17920E-05 2.20 060E-02 4.63210E-02 4.16930E-06 9.51210E-06 2.24750E-05 *AIR TEMP 21 MACRO 1 1 AIR 1 * ZR4_1_87 TEMP 21 MICRO 1 11 N14 O16 SNNAT FENAT CRNAT CNAT SINAT ZRNAT AL27 HFNAT H1 CONC 8.73002E-06 3.37265E-04 4.53892E-04 1.56 799E-04 8.95160E-05 4.22329E-05 1.39041E-05 4.24280E-02 2.83612E-0 6 1.22871E-06

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1.44796E-05 *EAU a 21 degres TEMP 21 MICRO 1 1 H2O CONC 0.0333609 FINC SECTION TOUT FIN ( WP *WP * Milieu 1 CONC. ATOMIQUES- %volumique 72 *H2O 0.0333597 * Milieu 2 CONC. ATOMIQUES- %volumique 28 *O16 3.37265E-04 *AL27 2.83612E-06 *FENAT 1.56799E-04 *SINAT 1.39041E-05 *N14 8.72999E-06 *SNNAT 4.53892E-04 *CRNAT 8.9516E-05 *CNAT 4.22329E-05 *HFNAT 1.22871E-06 *H1 1.44796E-05 *ZRNAT 0.042428 ) OPTION V6 GROUP 172 P5 TEMPER 21 FINOPTION MORET GEOM HOMO CHIMIE *WP TEMP 21 MICRO 1 12 H2O O16 AL27 FENAT SINAT N14 SNNAT CRNAT CNAT HFNAT H1 ZRNAT CONC 2.40190E-02 9.44342E-05 7.94114E-07 4.39037 E-05 3.89315E-06 2.44440E-06 1.27090E-04 2.50645E-05 1.18252E-0 5 3.44039E-07 4.05429E-06 1.18798E-02 FINC SECTION TOUT FIN ( WPG *WPG * Milieu 1 %-prop MASSIQUES- Dens= 2.67000007629395 - %volumique 70.5 *SINAT 0.004 *FENAT 0.004 *CUNAT 0.001 *MN55 0.005 *MGNAT 0.036 *CRNAT 0.003 *ZN64 0.002 *TINAT 0.0015 *AL27 0.9435 * Milieu 2 CONC. ATOMIQUES- %volumique 29.5 *N14 8.20622E-06 *O16 3.17029E-04 *SNNAT 4.26659E-04 *FENAT 1.47391E-04 *CRNAT 8.4145E-05 *CNAT 3.96989E-05 *SINAT 1.30699E-05 *ZRNAT 0.0398823 *AL27 2.66595E-06 *HFNAT 1.15499E-06 *H1 1.36108E-05 *H2O 2.00165E-03 ) OPTION V6 GROUP 172 P5 TEMPER 21 FINOPTION MORET GEOM HOMO CHIMIE *WPG TEMP 21

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MICRO 1 17 SINAT FENAT CUNAT MN55 MGNAT CRNAT ZN64 TINAT AL27 N14 O16 SNNAT CNAT ZRNAT HFNAT H1 H2O CONC 1.65301E-04 1.24672E-04 1.78386E-05 1.03168 E-04 1.67902E-03 9.02261E-05 3.54633E-05 3.55129E-05 3.96399E-0 2 2.42084E-06 9.35236E-05 1.25864E-04 1.17112E-05 1.17653E-0 2 3.40722E-07 4.01519E-06 5.90487E-04 FINC SECTION TOUT FIN ( AG3 + HOLES (water) *AG3 + HOLES (water) * Milieu 1 %-prop MASSIQUES- Dens= 2.67000007629395 - %volumique 70.5 *SINAT 0.004 *FENAT 0.004 *CUNAT 0.001 *MN55 0.005 *MGNAT 0.036 *CRNAT 0.003 *ZN64 0.002 *TINAT 0.0015 *AL27 0.9435 * Milieu 2 CONC. ATOMIQUES- %volumique 29.5 *H2O 0.0333597 ) OPTION V6 GROUP 172 P5 TEMPER 21 FINOPTION MORET GEOM HOMO CHIMIE *AG3 + HOLES (water) TEMP 21 MICRO 1 10 SINAT FENAT CUNAT MN55 MGNAT CRNAT ZN64 TINAT AL27 H2O CONC 1.61446E-04 8.11911E-05 1.78386E-05 1.03168 E-04 1.67902E-03 6.54033E-05 3.54633E-05 3.55129E-05 3.96391E-0 2 9.84111E-03 FINC SECTION TOUT FIND DEBUT_MORET4 LEU-COMP-THERM-STRUCTURE * Materials * 1 - Air * 2 - Steel Z2CN18-10 (AFNOR) * 3 - Water * 4 - AG3M (alluminium alloy) * 5 - AG3M + hole (air) * 6 - Titanium * 7 - AP (air+plug) * 9 - AC (air+clad+spring) * 10 - ACG (air+grid) * 11 - Array in air * 12 - Array in water * 13 - WP (water+plug) * 14 - WPG (water+plug+grid) * 15 - AG3M + hole (water) MINI 500 SIGM 0.0001 GEOM MODU 0 * plate TYPE 8 BOIT 93.0 93.0 1.25 VOLU 8 211 8 2 85 85 29 * tank

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* air TYPE 20 BOIT 95 95 110.0 VOLU 201 0 20 1 85 85 70 * water (value to modifie the water level) TYPE 21 PLAZ INFE 108.655 VOLU 211 231 21 3 0 0 75 ETSU 1 231 TYPE 23 BOIT 94.85 94.85 70 VOLU 231 201 23 1 85 85 70 ECRA 1 201 TYPE 24 BOIT 80 80 65 TROU 1 201 24 1 85 85 95.25 ECRA 2 231 211 FINM MODU 1 * universe TYPE 1 BOIT 80 80 65 VOLU 1 0 1 1 0.0 0.0 65.0 * grid * * 1st plate (right) TYPE 10 BOIT 12 12 0.2 OBLI 45 VOLU 101 88 10 15 17.32586 0 8.3 VOLU 102 1 10 5 17.32586 0 106.2 * 2nd plate (left) TYPE 14 BOIT 12 12 0.2 OBLI 45 VOLU 141 88 14 15 -17.32586 0 8.3 VOLU 142 1 14 5 -17.32586 0 106.2 * 3rd plate (lower) TYPE 18 BOIT 12 12 0.2 OBLI 45 VOLU 181 88 18 15 0 -17.32586 8.3 VOLU 182 1 18 5 0 -17.32586 106.2 * 4th plate (upper) TYPE 22 BOIT 12 12 0.2 OBLI 45 VOLU 221 88 22 15 0 17.32586 8.3 VOLU 222 1 22 5 0 17.32586 106.2 * material to test * 1st part of the cross TYPE 59 BOIT 18.2545 0.25124 50.00133 OBLI 45 VOLU 591 1 59 6 0 0 56.70133 ECRA 2 601 88 * 2nd part of the cross TYPE 60 BOIT 18.2545 0.25124 50.00133 OBLI -45 VOLU 601 1 60 6 0 0 56.70133 ECRA 1 88 * Fissile media * * Array in air TYPE 80 BOIT 8 8 50.731 OBLI 45 VOLU 801 1 80 11 -11.66901 0 58.051 ECRA 3 141 142 88 * left VOLU 802 1 80 11 11.66901 0 58.051 ECRA 3 101 102 8 8 * right VOLU 803 1 80 11 0 -11.66901 58.051 ECRA 3 181 182 88 * lower VOLU 804 1 80 11 0 11.66901 58.051 ECRA 3 221 222 8 8 * upper * AP (air+plug) TYPE 81 BOIT 8 8 0.734 OBLI 45 VOLU 811 801 81 7 -11.66901 0 108.048 VOLU 812 802 81 7 11.66901 0 108.048 VOLU 813 803 81 7 0 -11.66901 108.048 VOLU 814 804 81 7 0 11.66901 108.048

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* ACS (air+clad+spring) TYPE 83 BOIT 8 8 4.5245 OBLI 45 VOLU 831 801 83 9 -11.66901 0 102.7895 VOLU 832 802 83 9 11.66901 0 102.7895 VOLU 833 803 83 9 0 -11.66901 102.7895 VOLU 834 804 83 9 0 11.66901 102.7895 * AG (air+grid) TYPE 84 BOIT 8 8 0.2 OBLI 45 VOLU 841 831 84 10 -11.66901 0 106.2 VOLU 842 832 84 10 11.66901 0 106.2 VOLU 843 833 84 10 0 -11.66901 106.2 VOLU 844 834 84 10 0 11.66901 106.2 * Array in water (value to modifie the water level) TYPE 85 BOIT 8 8 35.5425 OBLI 45 VOLU 851 801 85 12 -11.66901 0 42.8625 VOLU 852 802 85 12 11.66901 0 42.8625 VOLU 853 803 85 12 0 -11.66901 42.8625 VOLU 854 804 85 12 0 11.66901 42.8625 * WP (water+plug) TYPE 86 BOIT 8 8 0.59 OBLI 45 VOLU 861 851 86 13 -11.66901 0 7.91 VOLU 862 852 86 13 11.66901 0 7.91 VOLU 863 853 86 13 0 -11.66901 7.91 VOLU 864 854 86 13 0 11.66901 7.91 * WPG (water+plug+grid) TYPE 87 BOIT 8 8 0.2 OBLI 45 VOLU 871 861 87 14 -11.66901 0 8.3 VOLU 872 862 87 14 11.66901 0 8.3 VOLU 873 863 87 14 0 -11.66901 8.3 VOLU 874 864 87 14 0 11.66901 8.3 * Water * tank (value to modifie the water level) TYPE 88 PLAZ INFE 78.405 VOLU 88 1 88 3 0 0 7 ETSU 1 1 FINM FING CHIMIE SEALINK 15 APO2 15 1 2 3 4 5 6 7 7 8 9 10 11 12 13 14 FINCHIMIE SORT CARA REDUIT ICSBEP ETENDU FCARA POST TAUX 1000 FPOS FSOR SOURCES UNIF 1000 MODU 1 FUNI FINSOURCES SIMU DEBU 200 FSIM

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FIND FIN_MORET4

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A.2 KENO-V.a - Input Listings

Comparisons calculations are performed with the KENO-V.a from the SCALE5.1 code systems using 238-group ENDF/B-VI.7 cross-sections data. 3100 batches and 5000 neutrons per batch are simulated. The first 100 batches are skipped from the simulation.

A.2.1 KENOV.A input listing for thin thickness configuration(4A-Ti-005).

=csas25 Programme materiaux, ecran en titane .50000 cm, HcE = 69.905 cm v6-238 read composition 'Fissile pellets u-234 1 0 7.10870E-06 300 end u-235 1 0 1.11040E-03 300 end u-236 1 0 3.17920E-05 300 end u-238 1 0 2.20060E-02 300 end o 1 0 4.63210E-02 300 end al 1 0 4.16930E-06 300 end fe-54 1 0 5.55982E-07 300 end fe-56 1 0 8.72773E-06 300 end fe-57 1 0 2.01561E-07 300 end fe-58 1 0 2.68241E-08 300 end si-28 1 0 2.07286E-05 300 end si-29 1 0 2.01561E-06 300 end si-30 1 0 6.93848E-07 300 end ' Fuel Clad zr-90 2 0 2.18292E-02 300 end zr-91 2 0 4.76042E-03 300 end zr-92 2 0 7.27640E-03 300 end zr-94 2 0 7.37399E-03 300 end zr-96 2 0 1.18798E-03 300 end fe-54 2 0 9.16488E-06 300 end fe-56 2 0 1.43869E-04 300 end fe-57 2 0 3.32256E-06 300 end fe-58 2 0 4.42172E-07 300 end cr-50 2 0 3.88948E-06 300 end cr-52 2 0 7.50047E-05 300 end cr-53 2 0 8.50493E-06 300 end cr-54 2 0 2.11706E-06 300 end o 2 0 3.37265E-04 300 end hf-174 2 0 1.96594E-09 300 end hf-176 2 0 6.46301E-08 300 end hf-177 2 0 2.28540E-07 300 end hf-178 2 0 3.35192E-07 300 end hf-179 2 0 1.67350E-07 300 end hf-180 2 0 4.31031E-07 300 end h 2 0 1.44796E-05 300 end si-28 2 0 1.28237E-05 300 end si-29 2 0 6.51156E-07 300 end si-30 2 0 4.29247E-07 300 end c 2 0 4.22329E-05 300 end al 2 0 2.83612E-06 300 end sn-112 2 0 4.40275E-06 300 end sn-114 2 0 2.99569E-06 300 end sn-115 2 0 1.54323E-06 300 end sn-116 2 0 6.59959E-05 300 end sn-117 2 0 3.48589E-05 300 end sn-118 2 0 1.09933E-04 300 end sn-119 2 0 3.89893E-05 300 end sn-120 2 0 1.47878E-04 300 end sn-122 2 0 2.10152E-05 300 end sn-124 2 0 2.62803E-05 300 end

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n 2 0 8.73002E-06 300 end ' Water h 3 0 6.67218E-02 300 end o 3 0 3.33609E-02 300 end 'Fissile pellets u-234 4 0 7.10870E-06 300 end u-235 4 0 1.11040E-03 300 end u-236 4 0 3.17920E-05 300 end u-238 4 0 2.20060E-02 300 end o 4 0 4.63210E-02 300 end al 4 0 4.16930E-06 300 end fe-54 4 0 5.55982E-07 300 end fe-56 4 0 8.72773E-06 300 end fe-57 4 0 2.01561E-07 300 end fe-58 4 0 2.68241E-08 300 end si-28 4 0 2.07286E-05 300 end si-29 4 0 2.01561E-06 300 end si-30 4 0 6.93848E-07 300 end ' Fuel Clad zr-90 5 0 2.18292E-02 300 end zr-91 5 0 4.76042E-03 300 end zr-92 5 0 7.27640E-03 300 end zr-94 5 0 7.37399E-03 300 end zr-96 5 0 1.18798E-03 300 end fe-54 5 0 9.16488E-06 300 end fe-56 5 0 1.43869E-04 300 end fe-57 5 0 3.32256E-06 300 end fe-58 5 0 4.42172E-07 300 end cr-50 5 0 3.88948E-06 300 end cr-52 5 0 7.50047E-05 300 end cr-53 5 0 8.50493E-06 300 end cr-54 5 0 2.11706E-06 300 end o 5 0 3.37265E-04 300 end hf-174 5 0 1.96594E-09 300 end hf-176 5 0 6.46301E-08 300 end hf-177 5 0 2.28540E-07 300 end hf-178 5 0 3.35192E-07 300 end hf-179 5 0 1.67350E-07 300 end hf-180 5 0 4.31031E-07 300 end h 5 0 1.44796E-05 300 end si-28 5 0 1.28237E-05 300 end si-29 5 0 6.51156E-07 300 end si-30 5 0 4.29247E-07 300 end c 5 0 4.22329E-05 300 end al 5 0 2.83612E-06 300 end sn-112 5 0 4.40275E-06 300 end sn-114 5 0 2.99569E-06 300 end sn-115 5 0 1.54323E-06 300 end sn-116 5 0 6.59959E-05 300 end sn-117 5 0 3.48589E-05 300 end sn-118 5 0 1.09933E-04 300 end sn-119 5 0 3.89893E-05 300 end sn-120 5 0 1.47878E-04 300 end sn-122 5 0 2.10152E-05 300 end sn-124 5 0 2.62803E-05 300 end n 5 0 8.73002E-06 300 end ' Air n 6 0 4.1985E-05 300 end o 6 0 1.1263E-05 300 end 'AG3 si-28 7 0 2.11207E-04 300 end si-29 7 0 1.07246E-05 300 end si-30 7 0 7.06972E-06 300 end Fe-54 7 0 6.73139E-06 300 end Fe-56 7 0 1.05668E-04 300 end Fe-57 7 0 2.44035E-06 300 end Fe-58 7 0 3.24765E-07 300 end

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cu-63 7 0 1.75020E-05 300 end cu-65 7 0 7.80088E-06 300 end mn 7 0 1.4633800E-04 300 end mg 7 0 2.38159E-03 300 end 'mg-24 7 0 1.88122E-03 300 end 'mg-25 7 0 2.38159E-04 300 end 'mg-26 7 0 2.62213E-04 300 end cr-50 7 0 4.03089E-06 300 end cr-52 7 0 7.77316E-05 300 end cr-53 7 0 8.81414E-06 300 end cr-54 7 0 2.19403E-06 300 end 'zn-64 7 0 4.91790E-05 300 end ti 7 0 5.03728E-05 300 end 'ti-46 7 0 4.02982E-06 300 end 'ti-47 7 0 3.67721E-06 300 end 'ti-48 7 0 3.71751E-05 300 end 'ti-49 7 0 2.77050E-06 300 end 'ti-50 7 0 2.72013E-06 300 end al 7 0 5.6225700E-02 300 end ' STEEL cr-50 8 0 7.15578E-04 300 end cr-52 8 0 1.37992E-02 300 end cr-53 8 0 1.56472E-03 300 end cr-54 8 0 3.89492E-04 300 end Ni-58 8 0 5.51838E-03 300 end Ni-60 8 0 2.12567E-03 300 end Ni-61 8 0 9.24014E-05 300 end Ni-62 8 0 2.94616E-04 300 end Ni-64 8 0 7.50301E-05 300 end Mn-55 8 0 8.65970E-04 300 end Si-28 8 0 1.56228E-03 300 end Si-29 8 0 7.93287E-05 300 end Si-30 8 0 5.22941E-05 300 end P-31 8 0 6.14380E-05 300 end S 8 0 4.45040E-05 300 end 'S-32 8 0 4.22476E-05 300 end 'S-33 8 0 3.38230E-07 300 end 'S-34 8 0 1.90922E-06 300 end 'S-36 8 0 8.90080E-09 300 end C 8 0 1.18830E-04 300 end FE-54 8 0 3.48046E-03 300 end FE-56 8 0 5.46358E-02 300 end FE-57 8 0 1.26178E-03 300 end FE-58 8 0 1.67920E-04 300 end ' Water h 9 0 6.67218E-02 300 end o 9 0 3.33609E-02 300 end 'titanium FE-54 10 0 3.37055E-06 300 end FE-56 10 0 5.33012E-05 300 end FE-57 10 0 1.27848E-06 300 end FE-58 10 0 1.62716E-07 300 end CR-50 10 0 5.42404E-07 300 end CR-52 10 0 1.04597E-05 300 end CR-53 10 0 1.18605E-06 300 end CR-54 10 0 2.95232E-07 300 end TI 10 0 5.62658E-02 300 end SN-112 10 0 3.97784E-09 300 end SN-114 10 0 2.66557E-09 300 end SN-115 10 0 1.39430E-09 300 end SN-116 10 0 5.95856E-08 300 end SN-117 10 0 3.14947E-08 300 end SN-118 10 0 9.93641E-08 300 end SN-119 10 0 3.52265E-08 300 end SN-120 10 0 1.33647E-07 300 end SN-122 10 0 1.89870E-08 300 end

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SN-124 10 0 2.37440E-08 300 end C 10 0 3.60273E-05 300 end n 10 0 3.86176E-06 300 end o 10 0 3.21174E-04 300 end al 10 0 1.50354E-06 300 end si 10 0 1.05926E-05 300 end P-31 10 0 8.12044E-07 300 end mn-55 10 0 1.37840E-06 300 end NI-58 10 0 3.45080E-06 300 end NI-60 10 0 1.32924E-06 300 end NI-61 10 0 5.77863E-08 300 end NI-62 10 0 1.84206E-07 300 end NI-64 10 0 4.69387E-08 300 end 'air 2 n 61 0 4.1985E-05 300 end o 61 0 1.1263E-05 300 end end composition read celldata infhommedium 7 end infhommedium 8 end infhommedium 9 end infhommedium 10 end infhommedium 61 end latticecell squarepitch fuelr=0.394595 1 gapr=0.418 0 cladr=0.474623 2 hpitch=0.8 3 end centrm data demin=0.2 end centrm latticecell squarepitch fuelr=0.394595 4 gapr=0.418 0 cladr=0.474623 5 hpitch=0.8 6 end centrm data demin=0.2 end centrm end celldata read parameters gen=3100 nsk=100 npg=5000 ' run=no plt=no flx=yes sig=0.0005 ' tsunami parameter block ' agn=10000 ' apg=30000 ' asg=0.0015 ' tfm=no ' nqd=0 ' pnm=2 ' mfx=yes ' msh=10 end parameters read geometry unit 1 com='Plug in water' zcylinder 2 1 0.474623 38.35 37.57 cuboid 9 1 0.8 -0.8 0.8 -0.8 38.35 30.25 unit 2 com='Plug in grid' zcylinder 2 1 0.474623 38.75 38.35 zcylinder 3 1 0.49 38.75 38.35 cuboid 7 1 0.8 -0.8 0.8 -0.8 38.75 38.35 unit 3 com='uo2 rod up to surface i.e. critical height' zcylinder 1 1 0.394595 108.655 38.75 zcylinder 0 1 0.418 108.655 38.75 zcylinder 2 1 0.474623 108.655 38.75 cuboid 3 1 0.8 -0.8 0.8 -0.8 108.655 38.7 5

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unit 4 com='uo2 rod, above surface' zcylinder 4 1 0.394595 128.515 108.655 zcylinder 0 1 0.418 128.515 108.655 zcylinder 5 1 0.474623 128.515 108.655 cuboid 6 1 0.8 -0.8 0.8 -0.8 128.515 108. 655 unit 5 com='Clad+Spring+Air above fissile below grid' zcylinder 0 1 0.418 136.25 128.515 zcylinder 5 1 0.474623 136.25 128.515 cuboid 61 1 0.8 -0.8 0.8 -0.8 136.25 128. 515 unit 6 com='Clad+Spring+grid' zcylinder 0 1 0.418 136.65 136.25 zcylinder 5 1 0.474623 136.65 136.25 zcylinder 61 1 0.49 136.65 136.25 cuboid 7 1 0.8 -0.8 0.8 -0.8 136.65 136.25 unit 7 com='Clad+Spring+Air abode fissile above grid' zcylinder 0 1 0.418 137.564 136.65 zcylinder 5 1 0.474623 137.564 136.65 cuboid 61 1 0.8 -0.8 0.8 -0.8 137.564 136.65 unit 8 com='Plug in air' zcylinder 5 1 0.474623 139.032 137.564 cuboid 61 1 0.8 -0.8 0.8 -0.8 139.032 137.564 unit 70 'reconstruction des combustibles sous eau array 1 0 0 30.25 unit 80 'reconstruction des combustibles sous air array 3 0 0 0 unit 94 com='plaque en acier sous l ensemble' cuboid 8 1 93 -93 93 -93 30.25 27.75 cuboid 9 1 95 -95 95 -95 30.25 0 unit 72 ' reseau sous eau + ecran' cuboid 10 1 0.25124 -0.25124 18.2545 -18.2545 108.6 55 36.95 cuboid 9 1 95 -95 95 -95 108.655 30.25 hole 721 -16.251241 -16.251241 0 hole 721 -16.251241 0.251241 0 hole 721 0.251241 0.251241 0 hole 721 0.251241 -16.251241 0 hole 722 0 0 0 hole 723 0 0 0 unit 721 '10x10 reseau eau' array 5 0 0 30.25 cuboid 9 1 16 0 16 0 108.655 30.25 unit 722 ' ecran gauche sous eau cuboid 10 1 -0.25124 -18.2545 0.25124 -0.25124 108. 655 36.95 unit 723 ' ecran droit sous eau cuboid 10 1 18.2545 0.25124 0.25124 -0.25124 108.65 5 36.95 unit 82 ' reseau sous air' cuboid 10 1 0.25124 -0.25124 18.2545 -18.2545 136. 95265 108.655

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cuboid 61 1 95 -95 95 -95 140 108.655 hole 821 -16.251241 -16.251241 0 hole 821 -16.251241 0.251241 0 hole 821 0.251241 0.251241 0 hole 821 0.251241 -16.251241 0 hole 822 0 0 0 hole 823 0 0 0 unit 821 com='10x10 reseau air' array 15 0 0 108.655 cuboid 61 1 16 0 16 0 139.032 108.655 unit 822 cuboid 10 1 -0.25124 -18.2545 0.25124 -0.25124 136. 95265 108.655 unit 823 cuboid 10 1 18.2545 0.25124 0.25124 -0.25124 136.9 5265 108.655 global unit 100 com='Whole parts' array 10 0 0 0 end geometry read array 'Array 1 ara=1 nux=1 nuy=1 nuz=3 com='UO2 fuel rod' fill 1 2 3 end fill 'Array 3 ara=3 nux=1 nuy=1 nuz=5 com='UO2 fuel rod air' fill 4 5 6 7 8 end fill 'Array 5 ara=5 nux=10 nuy=10 nuz=1 com='reseau sous eau' fill F70 end fill 'Array 15 ara=15 nux=10 nuy=10 nuz=1 com='reseau sous eau' fill F80 end fill 'Array 10 com='ensemble des parties' ara=10 nux=1 nuy=1 nuz=3 fill 94 72 82 end fill end array read bnds +xb=vacuum -xb=vacuum +yb=vacuum -yb=vacuum +zb=vacuum -zb=vacuum end bnds read plot ttl=' y=100' xul=0 yul=100 zul=141 xlr=190 ylr=100 zlr=0 nax=2000 uax=1 wdn=-1 lpi=10

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end plt1 ttl='x=100' xul=100 yul=0 zul=141 xlr=100 ylr=190 zlr=0 nax=2000 vax=1 wdn=-1 lpi=10 end plt2 ttl=' XY slice eau ' xul=0. yul=190 zul=45 xlr=190 ylr=0. zlr=45. uax=+1 vdn=-1 nax=2000 lpi=10 end plt3 ttl=' XY slice air' xul=0. yul=190 zul=111 xlr=190 ylr=0. zlr=111. uax=+1 vdn=-1 nax=2000 lpi=10 end plt4 ttl=' XY slice eau' xul=60. yul=130 zul=80 xlr=130 ylr=60. zlr=80 uax=+1 vdn=-1 nax=2000 lpi=10 end plt5 ttl=' XY slice eau' xul=80. yul=110 zul=130 xlr=110 ylr=80. zlr=130 uax=+1 vdn=-1 nax=2000 lpi=10 end plt6 ttl='x=84' xul=84 yul=0 zul=141 xlr=84 ylr=190 zlr=0 nax=2000 vax=1 wdn=-1 lpi=10 end plt7 end plot end data 'read sams ' nomix ' prtimp 'end sams end

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A.3 MCNPX - Input Listings Comparisons calculations are also performed with the MCNPX2.6 code using continuous energy ENDF/B-VII.0 cross-sections data. 4000 batches and 4000 neutrons per batch are simulated. The first 50 batches are skipped from the simulation.

A.3.1 MCNPX input listing for thin thickness configuration (4A-Ti-005) MESSAGE: xsdir=/home/leclaire/xsdir70 file name=4A-Ti-005 c reseau avec tous les materiaux sauf Zn64 et Pt n b atomes mcnp c four 10*10 reseau c critical water level c lattice pitch 1.6(cm); c c cellcards c 1 7 6.951250e-02 -30 36 -37 imp:n=1 u=1 $ cylindre fissile 2 1 5.324800E-05 -31 36 -38 #1 imp:n=1 u=1 $ cylindre air 3 8 4.354888E-02 -32 34 -39 #1 #2 imp:n=1 u=1 $ cylindre gaine 4 3 1.000827E-01 -33 35 -36 #1 #2 #3 imp:n=1 u=1 $ eau bas entre plaque et crayon 5 1 5.324800E-05 -33 40 -41 #1 #2 #3 imp:n=1 u=1 $ air haut entre plaque et crayon 6 4 5.93154E-02 -145 140 -146 142 35 -36 #1 #2 #3 #4 imp:n=1 u=1 $ grille bas 7 4 5.93154E-02 -145 140 -146 142 40 -41 #1 #2 #3 #5 imp:n=1 u=1 $ grille haut 8 3 1.000827E-01 -16 #1 #2 #3 #4 #5 #6 #7 imp:n=1 u=1 $ eau du reseau 9 1 5.324800E-05 16 32 #4 #5 #6 #7 imp:n=1 u=1 $ air du reseau 10 0 -145 140 -146 142 -39 128 imp:n=1 u=2 lat=1 f ill=0:9 0:9 0:0 1 99r 11 0 140 -121 142 -125 -39 128 imp:n=1 fill=2 12 like 11 but trcl (16.50248 0 0) 13 like 11 but trcl (0 16.50248 0) 14 like 11 but trcl (16.50248 16.50248 0) 20 5 5.67173E-02 (120 -123 125 -126 128 -129):(121 -122 124 -127 128 -129) & imp:n=1 $ ecran 30 2 8.69067E-02 -10 -11 12 13 14 -15 imp:n=1 $ plaque en steel 31 10 4.183385E-02 20 -121 22 -125 40 -41 #11 #12 # 13 #14 imp:n=1 $ grille haut 32 10 4.183385E-02 20 -121 126 -23 40 -41 #11 #12 # 13 #14 imp:n=1 $ grille haut 33 10 4.183385E-02 122 -21 126 -23 40 -41 #11 #12 # 13 #14 imp:n=1 $ grille haut 34 10 4.183385E-02 20 122 -21 22 -125 40 -41 #11 #1 2 #13 #14 imp:n=1 & $grille haut 35 9 7.134146E-02 20 -121 22 -125 35 -36 #11 #12 # 13 #14 imp:n=1 & $grille bas 36 9 7.134146E-02 20 -121 126 -23 35 -36 #11 #12 # 13 #14 imp:n=1 & $grille bas 37 9 7.134146E-02 122 -21 126 -23 35 -36 #11 #12 # 13 #14 imp:n=1 & $grille bas 38 9 7.134146E-02 20 122 -21 22 -125 35 -36 #11 #1 2 #13 #14 imp:n=1 & $grille bas 41 3 1.000827E-01 -1 -2 3 4 5 -16 #11 #12 #13 #14 #20 #30 #31 #32 #33 #34 & #35 #36 #37 #38 imp:n=1 $ ea u en dehors du reseau 42 1 5.324800E-05 -1 -2 3 4 16 -6 #11 #12 #13 #14 #20 #30 #31 #32 #33 #34 & #35 #36 #37 #38 imp:n=1 $ ai r en dehors du reseau 100 0 1:2:-3:-4:-5:6 imp:n=0 $ exterieur c surface cards c parallelpiped outer world 1 p 1 1 0 134.350288 2 p -1 1 0 134.350288 3 p 1 1 0 -134.350288 4 p -1 1 0 -134.350288 5 pz 0 6 pz 140 c c plaque steel 10 p 1 1 0 131.521861 11 p -1 1 0 131.521861 12 p 1 1 0 -131.521861 13 p -1 1 0 -131.521861

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14 pz 27.75 15 pz 30.25 c c water critical water level 16 pz 108.655 c c grille coordonnées x y 20 px -24.25124 21 px 24.25124 22 py -24.25124 23 py 24.25124 C c material to test 120 px -18.2545 121 px -0.25124 122 px 0.25124 123 px 18.2545 124 py -18.2545 125 py -0.25124 126 py 0.25124 127 py 18.2545 128 pz 36.95 129 pz 136.95265 c c 140 px -16.25124 141 px 16.25124 142 py -16.25124 143 py 16.25124 c pas reseau 145 px -14.65124 146 py -14.65124 c c c c CRAYONS 30 C/Z -15.45124 -15.45124 0.394595 $cyl fissil e 31 C/Z -15.45124 -15.45124 0.418 $cyl air 32 C/Z -15.45124 -15.45124 0.47463 $cyl gaine en zr 33 C/Z -15.45124 -15.45124 0.49 $cyl d'eau ou d'air entre plaque et crayon 34 pz 37.57 $z bas du crayon 35 pz 38.35 $z bas grille du bas 36 pz 38.75 $z haut grille du bas d e 0,4 cm (bas du combu) 37 pz 128.515 $z haut du comustible 38 pz 137.564 $z haut du cyl d'air ( debut du cyl de zr) 39 pz 139.032 $z haut du cyl de zr 40 pz 136.25 $z bas de la grille du haut 41 pz 136.65 $z haut de la grille d u haut c data cards c mode n $ transfort neutrons only c c material cards c c c air m1 7014.02c 4.19850E-05 $N14 8016.02c 1.12630E-05 $O16 c c steel m2 24050.02c 7.15578E-04 $cr50 24052.02c 1.37992E-02 $cr52 24053.02c 1.56472E-03 $cr53 24054.02c 3.89492E-04 $cr54 28058.02c 5.51838E-03 $Ni58 28060.02c 2.12567E-03 $Ni60 28061.02c 9.24014E-05 $Ni61 28062.02c 2.94616E-04 $Ni62 28064.02c 7.50301E-05 $Ni64 25055.02c 8.65970E-04 $Mn 14028.02c 1.56228E-03 $Si28 14029.02c 7.93287E-05 $Si29

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14030.02c 5.22941E-05 $Si30 15031.02c 6.14380E-05 $P31 16032.02c 4.22476E-05 $S32 16033.02c 3.38230E-07 $S33 16034.02c 1.90922E-06 $S34 16036.02c 8.90080E-09 $S36 6000.02c 1.18830E-04 $C 26054.02c 3.48046E-03 $FE54 26056.02c 5.46358E-02 $FE56 26057.02c 1.26178E-03 $FE57 26058.02c 1.67920E-04 $FE58 c c water(300k) m3 1001.02c 6.67218E-02 $H_H2O 8016.02c 3.33609E-02 $O16 mt3 lwtr01.70t $H eau legère à 300 K ( 01 indique la temp) c c AG3M m4 14028.02c 2.11207E-04 $SI 28 14029.02c 1.07246E-05 $SI 29 14030.02c 7.06972E-06 $SI 30 26054.02c 6.73139E-06 $FE54 26056.02c 1.05668E-04 $FE56 26057.02c 2.44035E-06 $FE57 26058.02c 3.24765E-07 $FE58 29063.02c 1.75020E-05 $CU 63 29065.02c 7.80088E-06 $CU 65 25055.02c 1.46338E-04 $MN55 12024.02c 1.88122E-03 $MG 24 12025.02c 2.38159E-04 $MG 25 12026.02c 2.62213E-04 $MG 26 24050.02c 4.03089E-06 $CR50 24052.02c 7.77316E-05 $CR52 24053.02c 8.81414E-06 $CR53 24054.02c 2.19403E-06 $CR54 30000.02c 4.91790E-05 $ zn 22046.02c 4.02982E-06 $TI 46 22047.02c 3.67721E-06 $TI 47 22048.02c 3.71751E-05 $TI 48 22049.02c 2.77050E-06 $TI 49 22050.02c 2.72013E-06 $TI 50 13027.02c 5.62257E-02 $AL27 c c ecran en Ti m5 26054.02c 3.37055E-06 $FE54 26056.02c 5.33012E-05 $FE56 26057.02c 1.27848E-06 $FE57 26058.02c 1.62716E-07 $FE58 24050.02c 5.42404E-07 $CR50 24052.02c 1.04597E-05 $CR52 24053.02c 1.18605E-06 $CR53 24054.02c 2.95232E-07 $CR54 22046.02c 4.50126E-03 $TI46 22047.02c 4.10740E-03 $TI47 22048.02c 4.15242E-02 $TI48 22049.02c 3.09462E-03 $TI49 22050.02c 3.03835E-03 $TI50 50112.02c 3.97784E-09 $SN112 50114.02c 2.66557E-09 $SN114 50115.02c 1.39430E-09 $SN115 50116.02c 5.95856E-08 $SN116 50117.02c 3.14947E-08 $SN117 50118.02c 9.93641E-08 $SN118 50119.02c 3.52265E-08 $SN119 50120.02c 1.33647E-07 $SN120 50122.02c 1.89870E-08 $SN122 50124.02c 2.37440E-08 $SN124 6000.02c 3.60273E-05 $C 7014.02c 3.86176E-06 $N14 8016.02c 3.21174E-04 $O16 13027.02c 1.50354E-06 $Al27 14028.02c 9.76955E-06 $si28 14029.02c 4.94674E-07 $si29

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14030.02c 3.28371E-07 $si30 15031.02c 8.12044E-07 $P31 25055.02c 1.37840E-06 $Mn55 28058.02c 3.45080E-06 $Ni58 28060.02c 1.32924E-06 $Ni60 28061.02c 5.77863E-08 $Ni61 28062.02c 1.84206E-07 $Ni62 28064.02c 4.69387E-08 $Ni64 c c fissile m7 92234.02c 7.10870E-06 $U234 92235.02c 1.11040E-03 $U235 92236.02c 3.17920E-05 $U236 92238.02c 2.20060E-02 $U238 8016.02c 4.63210E-02 $O16 13027.02c 4.16930E-06 $AL27 26054.02c 5.55982E-07 $FE54 26056.02c 8.72773E-06 $FE56 26057.02c 2.01561E-07 $FE57 26058.02c 2.68241E-08 $FE58 14028.02c 2.07286E-05 $SI 28 14029.02c 1.05255E-06 $SI 29 14030.02c 6.93848E-07 $SI 30 c c zircaloy m8 7014.02c 8.73002E-06 $N14 8016.02c 3.37265E-04 $O16 50112.02c 4.40275E-06 $SN112 50114.02c 2.99569E-06 $SN114 50115.02c 1.54323E-06 $SN115 50116.02c 6.59959E-05 $SN116 50117.02c 3.48589E-05 $SN117 50118.02c 1.09933E-04 $SN118 50119.02c 3.89893E-05 $SN119 50120.02c 1.47878E-04 $SN120 50122.02c 2.10152E-05 $SN122 50124.02c 2.62804E-05 $SN124 26054.02c 9.16488E-06 $FE54 26056.02c 1.43869E-04 $FE56 26057.02c 3.32256E-06 $FE57 26058.02c 4.42172E-07 $FE58 24050.02c 3.88948E-06 $CR50 24052.02c 7.50047E-05 $CR52 24053.02c 8.50493E-06 $CR53 24054.02c 2.11706E-06 $CR54 6000.02c 4.22329E-05 $C 14028.02c 1.28237E-05 $SI 28 14029.02c 6.51156E-07 $SI 29 14030.02c 4.29247E-07 $SI 30 40090.02c 2.18292E-02 $ZR 90 40091.02c 4.76042E-03 $ZR 91 40092.02c 7.27640E-03 $ZR 92 40094.02c 7.37399E-03 $ZR 94 40096.02c 1.18798E-03 $ZR 96 13027.02c 2.83612E-06 $AL27 72174.02c 1.96592E-09 $HF174 72176.02c 6.46296E-08 $HF176 72177.02c 2.28538E-07 $HF177 72178.02c 3.35189E-07 $HF178 72179.02c 1.67349E-07 $HF179 72180.02c 4.31028E-07 $HF180 1001.02c 1.44796E-05 $H1 c c AG3M+HOLES(W) grille avec trous eau bas m9 14028.02c 1.48901E-04 $SI 28 14029.02c 7.56084E-06 $SI 29 14030.02c 4.98416E-06 $SI 30 26054.02c 4.74562E-06 $FE54 26056.02c 7.44961E-05 $FE56 26057.02c 1.72044E-06 $FE57 26058.02c 2.28959E-07 $FE58 29063.02c 1.23390E-05 $CU 63 29065.02c 5.49964E-06 $CU 65

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25055.02c 1.03168E-04 $MN55 12024.02c 1.32626E-03 $MG 24 12025.02c 1.67902E-04 $MG 25 12026.02c 1.84860E-04 $MG 26 24050.02c 2.84177E-06 $CR50 24052.02c 5.48008E-05 $CR52 24053.02c 6.21397E-06 $CR53 24054.02c 1.54679E-06 $CR54 30000.02c 3.54633E-05 $ZN 22046.02c 2.84103E-06 $TI 46 22047.02c 2.59244E-06 $TI 47 22048.02c 2.62085E-05 $TI 48 22049.02c 1.95321E-06 $TI 49 22050.02c 1.91770E-06 $TI 50 13027.02c 3.96391E-02 $AL27 1001.02c 1.96822E-02 $H_H2O 8016.02c 9.84111E-03 $O16 mt9 lwtr01.70t $H eau legère à 300 K ( 01 indique la temp) c c c c AG3M+HOLES(A) grille avec trous air haut m10 14028.02c 1.48901E-04 $SI 28 14029.02c 7.56084E-06 $SI 29 14030.02c 4.98416E-06 $SI 30 26054.02c 4.74562E-06 $FE54 26056.02c 7.44961E-05 $FE56 26057.02c 1.72044E-06 $FE57 26058.02c 2.28959E-07 $FE58 29063.02c 1.23390E-05 $CU 63 29065.02c 5.49964E-06 $CU 65 25055.02c 1.03168E-04 $MN55 12024.02c 1.32626E-03 $MG 24 12025.02c 1.67902E-04 $MG 25 12026.02c 1.84860E-04 $MG 26 24050.02c 2.84177E-06 $CR50 24052.02c 5.48008E-05 $CR52 24053.02c 6.21397E-06 $CR53 24054.02c 1.54679E-06 $CR54 30000.02c 3.54633E-05 $ZN 22046.02c 2.84103E-06 $TI 46 22047.02c 2.59244E-06 $TI 47 22048.02c 2.62085E-05 $TI 48 22049.02c 1.95321E-06 $TI 49 22050.02c 1.91770E-06 $TI 50 13027.02c 3.96391E-02 $AL27 7014.02c 1.23856E-05 $N14 8016.02c 3.32259E-06 $O16 c c criticality cards c KCODE 4000 1.0 50 4000 c nb de sources par cycle, keff estimé, nb cycle no n pris en compte, c nb total de cycles c 1 source est placée en x y au centre de chaque cr ayon combustible c la cote z de la chaque est source est tirée aléat oirement entre c 38.75 et 128.515 c combu bas gauche KSRC -15.45124 -13.8499 39.7 10.6499 10.6499 89.2 PRINT -40

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A.4 MORET 5 - input listing

Comparisons calculations are also performed with the MORET 5 (under validation at IRSN) code using continuous energy JEF2.2 cross-sections data. The cross section library is based on JEF2.2 evaluation. 8000 batches and 8000 neutrons per batch are simulated. The first 200 batches are skipped.

A.4.1 MORET 5 input listing for thin thickness configuration (4A-Ti-005) DEBUT_MORET * Materials * 1 - Air * 2 - Steel Z2CN18-10 (AFNOR) * 3 - Water * 4 - AG3M (alluminium alloy) * 5 - AG3M + hole (air) * 6 - Cu * 7 - AP (air+plug) * 9 - AC (air+clad+spring) * 10 - ACG (air+grid) * 11 - Array in air * 12 - Array in water * 13 - WP (water+plug) * 14 - WPG (water+plug+grid) * 15 - AG3M + hole (water) ARREt ETAPes ACTIves 500 KEFF SIGMa 0.0003 FARRet * * ------------------------------------------------- ------------------- * CONNECTION APIJ NUMBER TO CHEMICAL MEDIUM NUMBER * ------------------------------------------------- ------------------- * * CHIMie * SEALink 20 APO2 20 1 2 3 4 5 6 7 8 9 10_0 10_1 10 _2 10_3 11_0 11_1 11_2 11_3 12 13 14 * FINChimie * * ------------------------------------------------- ------------------- * NEW CHEMICAL MEDIUMS DEFINING * ------------------------------------------------- ------------------- * CHIMie PONCtuel BIBLiotheque jef22.xml

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TEMP 293 * * * FOR THIS APPOLO CALCULATION * ------------------------------------------------- ------------------- * - Calcul number : 1 * - Calcul name : MILHOM1 * - Zone number : None * - Geometry type : CYLINDRE * * ------------------------------------------------- ------------------- * | No | Ext. radius | Name of medium | Tem perature | * ------------------------------------------------- ------------------- * | 1 | 1.0 | AIR | 21. | * ------------------------------------------------- ------------------- * * CHEMICAL MEDIUM DEFINING : COMP MILHOM1 CONCentration * 2 N14 4.198500E-05 O16 1.126300E-05 ENDComp * * * FOR THIS APPOLO CALCULATION * ------------------------------------------------- ------------------- * - Calcul number : 2 * - Calcul name : MILHOM2 * - Zone number : None * - Geometry type : CYLINDRE * * ------------------------------------------------- ------------------- * | No | Ext. radius | Name of medium | Tem perature | * ------------------------------------------------- ------------------- * | 1 | 1.0 | STEEL | 21. | * ------------------------------------------------- ------------------- * * CHEMICAL MEDIUM DEFINING : COMP MILHOM2 CONCentration * 22 C 1.18830E-04 CR50 7.15578E-04 CR52 1.37992E-02 CR53 1.56472E-03 CR54 3.89492E-04 FE54 3.48046E-03 FE56 5.46358E-02 FE57 1.26178E-03 FE58 1.67920E-04 MN55 8.65970E-04 NI58 5.51838E-03 NI60 2.12567E-03 NI61 9.24014E-05 NI62 2.94616E-04 NI64 7.50301E-05 P31 6.14380E-05 S32 4.45040E-05 SI 1.69390E-03 ENDComp * * * FOR THIS APPOLO CALCULATION * ------------------------------------------------- ------------------- * - Calcul number : 3 * - Calcul name : MILHOM3 * - Zone number : None * - Geometry type : CYLINDRE * * ------------------------------------------------- ------------------- * | No | Ext. radius | Name of medium | Tem perature | * ------------------------------------------------- ------------------- * | 1 | 1.0 | WATER | 21. | * ------------------------------------------------- ------------------- * * CHEMICAL MEDIUM DEFINING :

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COMP MILHOM3 CONCentration * 2 H1-H2O 6.672180E-02 O16 3.336090E-02 ENDComp * * * FOR THIS APPOLO CALCULATION * ------------------------------------------------- ------------------- * - Calcul number : 4 * - Calcul name : MILHOM4 * - Zone number : None * - Geometry type : CYLINDRE * * ------------------------------------------------- ------------------- * | No | Ext. radius | Name of medium | Tem perature | * ------------------------------------------------- ------------------- * | 1 | 1.0 | AG3 | 21. | * ------------------------------------------------- ------------------- * * CHEMICAL MEDIUM DEFINING : COMP MILHOM4 CONCentration * 15 AL27 5.622570E-02 CR50 4.030887E-06 CR52 7.773257E-05 CR53 8.813217E-06 CR54 2.194027E-06 CU 2.530290E-05 FE54 6.794735E-06 FE56 1.056293E-04 FE57 2.418465E-06 FE58 3.224620E-07 MG 2.381590E-03 MN55 1.463380E-04 SI 2.290010E-04 TI 5.037280E-05 * ZN64 5.030260E-05 ENDComp * * * FOR THIS APPOLO CALCULATION * ------------------------------------------------- ------------------- * - Calcul number : 5 * - Calcul name : MILHOM5 * - Zone number : None * - Geometry type : CYLINDRE * * ------------------------------------------------- ------------------- * | No | Ext. radius | Name of medium | Tem perature | * ------------------------------------------------- ------------------- * | 1 | 1.0 | AG3 + HOLES (air) | 21. | * ------------------------------------------------- ------------------- * * CHEMICAL MEDIUM DEFINING : COMP MILHOM5 CONCentration * 17 AL27 3.963910E-02 CR50 2.841773E-06 CR52 5.480143E-05 CR53 6.213314E-06 CR54 1.546788E-06 CU 1.783860E-05 FE54 4.790275E-06 FE56 7.446848E-05 FE57 1.705013E-06 FE58 2.273351E-07 MG 1.679020E-03 MN55 1.031680E-04 N14 1.238560E-05 O16 3.322590E-06 SI 1.614460E-04 TI 3.551290E-05 * ZN64 3.546330E-05 ENDComp *

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* * FOR THIS APPOLO CALCULATION * ------------------------------------------------- ------------------- * - Calcul number : 6 * - Calcul name : MILHOM6 * - Zone number : None * - Geometry type : CYLINDRE * * ------------------------------------------------- ------------------- * | No | Ext. radius | Name of medium | Tem perature | * ------------------------------------------------- ------------------- * | 1 | 1.0 | CU | 23. | * ------------------------------------------------- ------------------- * * CHEMICAL MEDIUM DEFINING : COMP MILHOM6 CONCentration * 12 FE54 3.37055E-06 FE56 5.33012E-05 FE57 1.27848E-06 FE58 1.62716E-07 CR50 5.42404E-07 CR52 1.04597E-05 CR53 1.18605E-06 CR54 2.95232E-07 TI 5.62658E-02 * SN112 3.97784E-09 SN114 2.66557E-09 SN115 1.39430E-09 SN116 5.95856E-08 SN117 3.14947E-08 SN118 9.93641E-08 SN119 3.52265E-08 SN120 1.33647E-07 SN122 1.89870E-08 SN124 2.37440E-08 C 3.60273E-05 N14 3.86176E-06 O16 3.21174E-04 AL27 1.50354E-06 SI 1.05926E-05 P31 8.12044E-07 MN55 1.37840E-06 NI58 3.45080E-06 NI60 1.32924E-06 NI61 5.77863E-08 NI62 1.84206E-07 NI64 4.69387E-08 ENDComp * * * FOR THIS APPOLO CALCULATION * ------------------------------------------------- ------------------- * - Calcul number : 7 * - Calcul name : MILHOM7 * - Zone number : None * - Geometry type : CYLINDRE * * ------------------------------------------------- ------------------- * | No | Ext. radius | Name of medium | Tem perature | * ------------------------------------------------- ------------------- * | 1 | 1.0 | AP | 21. | * ------------------------------------------------- ------------------- * * CHEMICAL MEDIUM DEFINING : COMP MILHOM7 CONCentration * 31 AL27 7.941140E-07 C 1.182520E-05 CR50 1.089053E-06 CR52 2.100154E-05 CR53 2.381128E-06 CR54 5.927754E-07 FE54 2.590318E-06 FE56 4.026847E-05

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FE57 9.219777E-07 FE58 1.229304E-07 H1 4.054290E-06 HF174 5.573432E-10 HF176 1.791067E-08 HF177 6.401190E-08 HF178 9.391233E-08 HF179 4.688908E-08 HF180 1.207577E-07 N14 3.267360E-05 O16 1.025440E-04 SI 3.893150E-06 * SN112 1.232773E-06 SN114 8.260850E-07 SN115 4.575240E-07 SN116 1.846618E-05 SN117 9.760512E-06 SN118 3.078120E-05 SN119 1.090432E-05 SN120 4.141863E-05 SN122 5.884267E-06 SN124 7.358511E-06 ZR 1.187980E-02 ENDComp * * * FOR THIS APPOLO CALCULATION * ------------------------------------------------- ------------------- * - Calcul number : 8 * - Calcul name : MILHOM8 * - Zone number : None * - Geometry type : CYLINDRE * * ------------------------------------------------- ------------------- * | No | Ext. radius | Name of medium | Tem perature | * ------------------------------------------------- ------------------- * | 1 | 1.0 | milieu_23 | 21. | * ------------------------------------------------- ------------------- * * CHEMICAL MEDIUM DEFINING : COMP MILHOM8 CONCentration * 31 AL27 1.759100E-07 C 2.619500E-06 CR50 2.412444E-07 CR52 4.652214E-06 CR53 5.274619E-07 CR54 1.313102E-07 FE54 5.738021E-07 FE56 8.920192E-06 FE57 2.042347E-07 FE58 2.723129E-08 H1 8.980970E-07 HF174 1.234613E-10 HF176 3.967529E-09 HF177 1.417976E-08 HF178 2.080323E-08 HF179 1.038676E-08 HF180 2.674996E-08 N14 3.992240E-05 O16 3.148330E-05 SI 8.624020E-07 * SN112 2.730812E-07 SN114 1.829925E-07 SN115 1.013497E-07 SN116 4.090587E-06 SN117 2.162127E-06 SN118 6.818584E-06 SN119 2.415502E-06 SN120 9.174965E-06 SN122 1.303470E-06 SN124 1.630041E-06 ZR 2.631600E-03 ENDComp

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* * * FOR THIS APPOLO CALCULATION * ------------------------------------------------- ------------------- * - Calcul number : 9 * - Calcul name : MILHOM9 * - Zone number : None * - Geometry type : CYLINDRE * * ------------------------------------------------- ------------------- * | No | Ext. radius | Name of medium | Tem perature | * ------------------------------------------------- ------------------- * | 1 | 1.0 | milieu_24 | 21. | * ------------------------------------------------- ------------------- * * CHEMICAL MEDIUM DEFINING : COMP MILHOM9 CONCentration * 36 AL27 3.965910E-02 C 2.619500E-06 CR50 3.084442E-06 CR52 5.948110E-05 CR53 6.743889E-06 CR54 1.678873E-06 CU 1.784750E-05 FE54 5.366487E-06 FE56 8.342613E-05 FE57 1.910105E-06 FE58 2.546807E-07 H1 8.980970E-07 HF174 1.234613E-10 HF176 3.967529E-09 HF177 1.417976E-08 HF178 2.080323E-08 HF179 1.038676E-08 HF180 2.674996E-08 MG 1.679860E-03 MN55 1.032200E-04 N14 1.030810E-05 O16 2.353890E-05 SI 1.623890E-04 * SN112 2.730812E-07 SN114 1.829925E-07 SN115 1.013497E-07 SN116 4.090587E-06 SN117 2.162127E-06 SN118 6.818584E-06 SN119 2.415502E-06 SN120 9.174965E-06 SN122 1.303470E-06 SN124 1.630041E-06 TI 3.553060E-05 * ZN64 3.548110E-05 ZR 2.631600E-03 ENDComp * * * FOR THIS APPOLO CALCULATION * ------------------------------------------------- ------------------- * - Calcul number : 10 * - Calcul name : CELLUL10 * - Zone number : 0 * - Geometry type : CYLINDRE * * ------------------------------------------------- ------------------- * | No | Ext. radius | Name of medium | Tem perature | * ------------------------------------------------- ------------------- * | 1 | 0.279021 | FISSIL1_ 1 | 21. | * | 2 | 0.352936 | FISSIL1_ 2 | 21. | * | 3 | 0.384604 | FISSIL1_ 3 | 21. | * | 4 | 0.394595 | FISSIL1_ 4 | 21. | * ------------------------------------------------- ------------------- * * CHEMICAL MEDIUM DEFINING :

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COMP CELLUL10_0 CONCentration * 11 AL27 4.16930E-06 FE54 5.55982E-07 FE56 8.72773E-06 FE57 2.01561E-07 FE58 2.68241E-08 O16 4.632100E-02 SI 2.247500E-05 U234 7.108700E-06 U235 1.110400E-03 U236 3.179200E-05 U238 2.200600E-02 ENDComp * * * FOR THIS APPOLO CALCULATION * ------------------------------------------------- ------------------- * - Calcul number : 10 * - Calcul name : CELLUL10 * - Zone number : 1 * - Geometry type : CYLINDRE * * ------------------------------------------------- ------------------- * | No | Ext. radius | Name of medium | Tem perature | * ------------------------------------------------- ------------------- * | 5 | 0.418 | STRUCT1 | 21. | * ------------------------------------------------- ------------------- * * CHEMICAL MEDIUM DEFINING : COMP CELLUL10_1 CONCentration * 2 N14 4.198500E-05 O16 1.126300E-05 ENDComp * * * FOR THIS APPOLO CALCULATION * ------------------------------------------------- ------------------- * - Calcul number : 10 * - Calcul name : CELLUL10 * - Zone number : 2 * - Geometry type : CYLINDRE * * ------------------------------------------------- ------------------- * | No | Ext. radius | Name of medium | Tem perature | * ------------------------------------------------- ------------------- * | 6 | 0.474623 | STRUCT2 | 21. | * ------------------------------------------------- ------------------- * * CHEMICAL MEDIUM DEFINING : COMP CELLUL10_2 CONCentration * 31 AL27 2.836120E-06 C 4.223290E-05 CR50 3.889470E-06 CR52 7.500546E-05 CR53 8.504020E-06 CR54 2.117053E-06 FE54 9.251141E-06 FE56 1.438160E-04 FE57 3.292779E-06 FE58 4.390372E-07 H1 1.447960E-05 HF174 1.990510E-09 HF176 6.396664E-08 HF177 2.286138E-07 HF178 3.354010E-07 HF179 1.674609E-07 HF180 4.312772E-07 N14 8.730020E-06 O16 3.372650E-04 SI 1.390410E-05 * SN112 4.402752E-06 SN114 2.950298E-06 SN115 1.634011E-06

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SN116 6.595051E-05 SN117 3.485891E-05 SN118 1.099326E-04 SN119 3.894393E-05 SN120 1.479234E-04 SN122 2.101520E-05 SN124 2.628035E-05 ZR 4.242800E-02 ENDComp * * * FOR THIS APPOLO CALCULATION * ------------------------------------------------- ------------------- * - Calcul number : 10 * - Calcul name : CELLUL10 * - Zone number : 3 * - Geometry type : CYLINDRE * * ------------------------------------------------- ------------------- * | No | Ext. radius | Name of medium | Tem perature | * ------------------------------------------------- ------------------- * | 7 | 0.581643 | STRUCT3 | 21. | * | 8 | 0.688663 | STRUCT3 | 21. | * | 9 | 0.795683 | STRUCT3 | 21. | * | 10 | 0.902703 | STRUCT3 | 21. | * ------------------------------------------------- ------------------- * * CHEMICAL MEDIUM DEFINING : COMP CELLUL10_3 CONCentration * 2 N14 4.198500E-05 O16 1.126300E-05 ENDComp * * * FOR THIS APPOLO CALCULATION * ------------------------------------------------- ------------------- * - Calcul number : 11 * - Calcul name : CELLUL11 * - Zone number : 0 * - Geometry type : CYLINDRE * * ------------------------------------------------- ------------------- * | No | Ext. radius | Name of medium | Tem perature | * ------------------------------------------------- ------------------- * | 1 | 0.279021 | FISSIL1_ 1 | 21. | * | 2 | 0.352936 | FISSIL1_ 2 | 21. | * | 3 | 0.384604 | FISSIL1_ 3 | 21. | * | 4 | 0.394595 | FISSIL1_ 4 | 21. | * ------------------------------------------------- ------------------- * * CHEMICAL MEDIUM DEFINING : COMP CELLUL11_0 CONCentration * 11 AL27 4.16930E-06 FE54 5.55982E-07 FE56 8.72773E-06 FE57 2.01561E-07 FE58 2.68241E-08 O16 4.632100E-02 SI 2.247500E-05 U234 7.108700E-06 U235 1.110400E-03 U236 3.179200E-05 U238 2.200600E-02 ENDComp * * * FOR THIS APPOLO CALCULATION * ------------------------------------------------- ------------------- * - Calcul number : 11 * - Calcul name : CELLUL11 * - Zone number : 1 * - Geometry type : CYLINDRE *

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* ------------------------------------------------- ------------------- * | No | Ext. radius | Name of medium | Tem perature | * ------------------------------------------------- ------------------- * | 5 | 0.418 | STRUCT1 | 21. | * ------------------------------------------------- ------------------- * * CHEMICAL MEDIUM DEFINING : COMP CELLUL11_1 CONCentration * 2 N14 4.198500E-05 O16 1.126300E-05 ENDComp * * * FOR THIS APPOLO CALCULATION * ------------------------------------------------- ------------------- * - Calcul number : 11 * - Calcul name : CELLUL11 * - Zone number : 2 * - Geometry type : CYLINDRE * * ------------------------------------------------- ------------------- * | No | Ext. radius | Name of medium | Tem perature | * ------------------------------------------------- ------------------- * | 6 | 0.474623 | STRUCT2 | 21. | * ------------------------------------------------- ------------------- * * CHEMICAL MEDIUM DEFINING : COMP CELLUL11_2 CONCentration * 31 AL27 2.836120E-06 C 4.223290E-05 CR50 3.889470E-06 CR52 7.500546E-05 CR53 8.504020E-06 CR54 2.117053E-06 FE54 9.251141E-06 FE56 1.438160E-04 FE57 3.292779E-06 FE58 4.390372E-07 H1 1.447960E-05 HF174 1.990510E-09 HF176 6.396664E-08 HF177 2.286138E-07 HF178 3.354010E-07 HF179 1.674609E-07 HF180 4.312772E-07 N14 8.730020E-06 O16 3.372650E-04 SI 1.390410E-05 * SN112 4.402752E-06 SN114 2.950298E-06 SN115 1.634011E-06 SN116 6.595051E-05 SN117 3.485891E-05 SN118 1.099326E-04 SN119 3.894393E-05 SN120 1.479234E-04 SN122 2.101520E-05 SN124 2.628035E-05 ZR 4.242800E-02 ENDComp * * * FOR THIS APPOLO CALCULATION * ------------------------------------------------- ------------------- * - Calcul number : 11 * - Calcul name : CELLUL11 * - Zone number : 3 * - Geometry type : CYLINDRE * * ------------------------------------------------- ------------------- * | No | Ext. radius | Name of medium | Tem perature | * ------------------------------------------------- ------------------- * | 7 | 0.581643 | STRUCT3 | 21. |

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* | 8 | 0.688663 | STRUCT3 | 21. | * | 9 | 0.795683 | STRUCT3 | 21. | * | 10 | 0.902703 | STRUCT3 | 21. | * ------------------------------------------------- ------------------- * * CHEMICAL MEDIUM DEFINING : COMP CELLUL11_3 CONCentration * 2 H1-H2O 6.671940E-02 O16 3.335970E-02 ENDComp * * * FOR THIS APPOLO CALCULATION * ------------------------------------------------- ------------------- * - Calcul number : 12 * - Calcul name : MILHOM10 * - Zone number : None * - Geometry type : CYLINDRE * * ------------------------------------------------- ------------------- * | No | Ext. radius | Name of medium | Tem perature | * ------------------------------------------------- ------------------- * | 1 | 1.0 | WP | 21. | * ------------------------------------------------- ------------------- * * CHEMICAL MEDIUM DEFINING : COMP MILHOM10 CONCentration * 32 AL27 7.941140E-07 C 1.182520E-05 CR50 1.089053E-06 CR52 2.100154E-05 CR53 2.381128E-06 CR54 5.927754E-07 FE54 2.590318E-06 FE56 4.026847E-05 FE57 9.219777E-07 FE58 1.229304E-07 H1 4.054290E-06 H1-H2O 4.803800E-02 HF174 5.573432E-10 HF176 1.791067E-08 HF177 6.401190E-08 HF178 9.391233E-08 HF179 4.688908E-08 HF180 1.207577E-07 N14 2.444400E-06 O16 2.411343E-02 SI 3.893150E-06 * SN112 1.232773E-06 SN114 8.260850E-07 SN115 4.575240E-07 SN116 1.846618E-05 SN117 9.760512E-06 SN118 3.078120E-05 SN119 1.090432E-05 SN120 4.141863E-05 SN122 5.884267E-06 SN124 7.358511E-06 ZR 1.187980E-02 ENDComp * * * FOR THIS APPOLO CALCULATION * ------------------------------------------------- ------------------- * - Calcul number : 13 * - Calcul name : MILHOM11 * - Zone number : None * - Geometry type : CYLINDRE * * ------------------------------------------------- ------------------- * | No | Ext. radius | Name of medium | Tem perature | * ------------------------------------------------- ------------------- * | 1 | 1.0 | WPG | 21. |

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* ------------------------------------------------- ------------------- * * CHEMICAL MEDIUM DEFINING : COMP MILHOM11 CONCentration * 37 AL27 3.963990E-02 C 1.171120E-05 CR50 3.920324E-06 CR52 7.560045E-05 CR53 8.571480E-06 CR54 2.133847E-06 CU 1.783860E-05 FE54 7.355648E-06 FE56 1.143492E-04 FE57 2.618112E-06 FE58 3.490816E-07 H1 4.015190E-06 H1-H2O 1.180974E-03 HF174 5.519696E-10 HF176 1.773799E-08 HF177 6.339474E-08 HF178 9.300688E-08 HF179 4.643700E-08 HF180 1.195934E-07 MG 1.679020E-03 MN55 1.031680E-04 N14 2.420840E-06 O16 6.840106E-04 SI 1.653010E-04 * SN112 1.220881E-06 SN114 8.181160E-07 SN115 4.531104E-07 SN116 1.828804E-05 SN117 9.666355E-06 SN118 3.048426E-05 SN119 1.079913E-05 SN120 4.101908E-05 SN122 5.827503E-06 SN124 7.287526E-06 TI 3.551290E-05 * ZN64 3.546330E-05 ZR 1.176530E-02 ENDComp * * * FOR THIS APPOLO CALCULATION * ------------------------------------------------- ------------------- * - Calcul number : 14 * - Calcul name : MILHOM12 * - Zone number : None * - Geometry type : CYLINDRE * * ------------------------------------------------- ------------------- * | No | Ext. radius | Name of medium | Tem perature | * ------------------------------------------------- ------------------- * | 1 | 1.0 | AG3 + HOLES (water) | 21. | * ------------------------------------------------- ------------------- * * CHEMICAL MEDIUM DEFINING : COMP MILHOM12 CONCentration * 17 AL27 3.963910E-02 CR50 2.841773E-06 CR52 5.480143E-05 CR53 6.213314E-06 CR54 1.546788E-06 CU 1.783860E-05 FE54 4.790275E-06 FE56 7.446848E-05 FE57 1.705013E-06 FE58 2.273351E-07 H1-H2O 1.968222E-02 MG 1.679020E-03 MN55 1.031680E-04 O16 9.841110E-03

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SI 1.614460E-04 TI 3.551290E-05 * ZN64 3.546330E-05 ENDComp FINChimie * GEOM MODU 0 * plate TYPE 8 BOIT 93.0 93.0 1.25 OBLI -45 VOLU 8 211 8 2 85 85 29 * tank * air TYPE 20 BOIT 95 95 110.0 OBLI -45 VOLU 201 0 20 1 85 85 70 * water (value to modifie the water level) TYPE 21 PLAZ INFE 108.655 VOLU 211 231 21 3 0 0 0 ETSU 1 231 TYPE 23 BOIT 94.85 94.85 70 OBLI -45 VOLU 231 201 23 1 85 85 70 TYPE 24 BOIT 80 80 65 OBLI -45 TROU 1 201 24 1 85 85 95.25 ECRA 2 231 211 FINM MODU 1 * universe TYPE 1 BOIT 80 80 65 OBLI -45 VOLU 1 0 1 1 0.0 0.0 65.0 * grid * * 1st plate (right) TYPE 10 BOIT 12 12 0.2 VOLU 101 88 10 20 12.25 -12.25 8.3 VOLU 102 1 10 5 12.25 -12.25 106.2 * 2nd plate (left) TYPE 14 BOIT 12 12 0.2 VOLU 141 88 14 20 -12.25 12.25 8.3 VOLU 142 1 14 5 -12.25 12.25 106.2 * 3rd plate (lower) TYPE 18 BOIT 12 12 0.2 VOLU 181 88 18 20 -12.25 -12.25 8.3 VOLU 182 1 18 5 -12.25 -12.25 106.2 * 4th plate (upper) TYPE 22 BOIT 12 12 0.2 VOLU 221 88 22 20 12.25 12.25 8.3 VOLU 222 1 22 5 12.25 12.25 106.2 * material to test * 1st part of the cross TYPE 59 BOIT 18.2475 0.2499 49.9945 VOLU 591 1 59 6 0 0 56.6945 ECRA 2 601 88 * 2nd part of the cross TYPE 60 BOIT 0.2499 18.2475 49.9945 VOLU 601 1 60 6 0 0 56.6945 ECRA 1 88 * Fissile media * * Array in air TYPE 80 BOIT 8 8 50.731 * left TYPE 801 BOIT 8 8 9.93 TROU 801 1 801 6 -8.25 8.25 88.335 ECRA 1 88 * right TYPE 802 BOIT 8 8 9.93 TROU 802 1 802 7 8.25 -8.25 88.335 ECRA 1 88 * lower TYPE 803 BOIT 8 8 9.93 TROU 803 1 803 8 -8.25 -8.25 88.335 ECRA 1 88 * upper TYPE 804 BOIT 8 8 9.93 TROU 804 1 804 9 8.25 8.25 88.335 ECRA 1 88 * AP (air+plug) TYPE 81 BOIT 8 8 0.734 TYPE 811 BOIT 8 8 0.7340 VOLU 811 1 811 7 -8.25 8.25 108.0480

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TYPE 812 BOIT 8 8 0.7340 VOLU 812 1 812 7 8.25 -8.25 108.0480 TYPE 813 BOIT 8 8 0.7340 VOLU 813 1 813 7 -8.25 -8.25 108.0480 TYPE 814 BOIT 8 8 0.7340 VOLU 814 1 814 7 8.25 8.25 108.0480 * ACS (air+clad+spring) TYPE 83 BOIT 8 8 4.5245 TYPE 831 BOIT 8 8 4.5245 VOLU 831 1 831 8 -8.25 8.25 102.7895 ECRA 1 142 TYPE 832 BOIT 8 8 4.5245 VOLU 832 1 832 8 8.25 -8.25 102.7895 ECRA 1 102 TYPE 833 BOIT 8 8 4.5245 VOLU 833 1 833 8 -8.25 -8.25 102.7895 ECRA 1 182 TYPE 834 BOIT 8 8 4.5245 VOLU 834 1 834 8 8.25 8.25 102.7895 ECRA 1 222 * AG (air+grid) TYPE 84 BOIT 8 8 0.2 VOLU 841 831 84 9 -8.25 8.25 106.2 VOLU 842 832 84 9 8.25 -8.25 106.2 VOLU 843 833 84 9 -8.25 -8.25 106.2 VOLU 844 834 84 9 8.25 8.25 106.2 * Array in water (value to modifie the water level) TYPE 85 BOIT 8 8 34.9525 TYPE 851 BOIT 8 8 34.9525 TROU 851 88 851 2 -8.25 8.25 43.4525 TYPE 852 BOIT 8 8 34.9525 TROU 852 88 852 3 8.25 -8.25 43.4525 TYPE 853 BOIT 8 8 34.9525 TROU 853 88 853 4 -8.25 -8.25 43.4525 TYPE 854 BOIT 8 8 34.9525 TROU 854 88 854 5 8.25 8.25 43.4525 * WP (water+plug) TYPE 86 BOIT 8 8 0.59 TYPE 861 BOIT 8 8 0.5900 VOLU 861 88 861 18 -8.25 8.25 7.9100 ECRA 1 141 TYPE 862 BOIT 8 8 0.5900 VOLU 862 88 862 18 8.25 -8.25 7.9100 ECRA 1 101 TYPE 863 BOIT 8 8 0.5900 VOLU 863 88 863 18 -8.25 -8.25 7.9100 ECRA 1 181 TYPE 864 BOIT 8 8 0.5900 VOLU 864 88 864 18 8.25 8.25 7.9100 ECRA 1 221 * WPG (water+plug+grid) TYPE 87 BOIT 8 8 0.2 VOLU 871 861 87 19 -8.25 8.25 8.3 VOLU 872 862 87 19 8.25 -8.25 8.3 VOLU 873 863 87 19 -8.25 -8.25 8.3 VOLU 874 864 87 19 8.25 8.25 8.3 * Water * tank (value to modifie the water level) TYPE 88 PLAZ INFE 78.405 VOLU 88 1 88 3 0 0 0 ETSU 1 1 FINM * * MODU 2 * * External lattice's Volume TYPE 851 BOIT 8 8 34.9525 VOLUME 851 0 851 17 -11.6671 0 43.4525 * * Lattice's principal mesh Volume TYPE 8511 BOITe 0.800000 0.800000 34.9525 VOLUME 8511 851 8511 17 -18.867100 -7.200000 43.45 25

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* * Rods and sheaths in the principal mesh TYPE 8512 CYLZ 0.474623 34.9525 VOLUME 8512 8511 8512 16 -18.867100 -7.200000 43.4 525 TYPE 8513 CYLZ 0.418 34.9525 VOLUME 8513 8512 8513 15 -18.867100 -7.200000 43.4 525 TYPE 8514 CYLZ 0.394595 34.9525 VOLUME 8514 8513 8514 14 -18.867100 -7.200000 43.4 525 * * LATTICE's Parameters RESC MPRI 8511 DIMR 10 10 1 INDP 1 1 1 FINR * FINM * * * * MODU 3 * * External lattice's Volume TYPE 852 BOIT 8 8 34.9525 VOLUME 852 0 852 17 11.6671 0 43.4525 * * Lattice's principal mesh Volume TYPE 8521 BOITe 0.800000 0.800000 34.9525 VOLUME 8521 852 8521 17 4.467100 -7.200000 43.4525 * * Rods and sheaths in the principal mesh TYPE 8522 CYLZ 0.474623 34.9525 VOLUME 8522 8521 8522 16 4.467100 -7.200000 43.452 5 TYPE 8523 CYLZ 0.418 34.9525 VOLUME 8523 8522 8523 15 4.467100 -7.200000 43.452 5 TYPE 8524 CYLZ 0.394595 34.9525 VOLUME 8524 8523 8524 14 4.467100 -7.200000 43.452 5 * * LATTICE's Parameters RESC MPRI 8521 DIMR 10 10 1 INDP 1 1 1 FINR * FINM * * * *

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MODU 4 * * External lattice's Volume TYPE 853 BOIT 8 8 34.9525 VOLUME 853 0 853 17 0 -11.6671 43.4525 * * Lattice's principal mesh Volume TYPE 8531 BOITe 0.800000 0.800000 34.9525 VOLUME 8531 853 8531 17 -7.200000 -18.867100 43.45 25 * * Rods and sheaths in the principal mesh TYPE 8532 CYLZ 0.474623 34.9525 VOLUME 8532 8531 8532 16 -7.200000 -18.867100 43.4 525 TYPE 8533 CYLZ 0.418 34.9525 VOLUME 8533 8532 8533 15 -7.200000 -18.867100 43.4 525 TYPE 8534 CYLZ 0.394595 34.9525 VOLUME 8534 8533 8534 14 -7.200000 -18.867100 43.4 525 * * LATTICE's Parameters RESC MPRI 8531 DIMR 10 10 1 INDP 1 1 1 FINR * FINM * * * * MODU 5 * * External lattice's Volume TYPE 854 BOIT 8 8 34.9525 VOLUME 854 0 854 17 0 11.6671 43.4525 * * Lattice's principal mesh Volume TYPE 8541 BOITe 0.800000 0.800000 34.9525 VOLUME 8541 854 8541 17 -7.200000 4.467100 43.4525 * * Rods and sheaths in the principal mesh TYPE 8542 CYLZ 0.474623 34.9525 VOLUME 8542 8541 8542 16 -7.200000 4.467100 43.452 5 TYPE 8543 CYLZ 0.418 34.9525 VOLUME 8543 8542 8543 15 -7.200000 4.467100 43.452 5 TYPE 8544 CYLZ 0.394595 34.9525 VOLUME 8544 8543 8544 14 -7.200000 4.467100 43.452 5 * * LATTICE's Parameters

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RESC MPRI 8541 DIMR 10 10 1 INDP 1 1 1 FINR * FINM * * * * MODU 6 * * External lattice's Volume TYPE 801 BOIT 8 8 9.93 VOLUME 801 0 801 13 -11.6671 0 88.335 * * Lattice's principal mesh Volume TYPE 8011 BOITe 0.800000 0.800000 9.93 VOLUME 8011 801 8011 13 -18.867100 -7.200000 88.33 5 * * Rods and sheaths in the principal mesh TYPE 8012 CYLZ 0.474623 9.93 VOLUME 8012 8011 8012 12 -18.867100 -7.200000 88.3 35 TYPE 8013 CYLZ 0.418 9.93 VOLUME 8013 8012 8013 11 -18.867100 -7.200000 88.3 35 TYPE 8014 CYLZ 0.394595 9.93 VOLUME 8014 8013 8014 10 -18.867100 -7.200000 88.3 35 * * LATTICE's Parameters RESC MPRI 8011 DIMR 10 10 1 INDP 1 1 1 FINR * FINM * * * * MODU 7 * * External lattice's Volume TYPE 802 BOIT 8 8 9.93 VOLUME 802 0 802 13 11.6671 0 88.335 * * Lattice's principal mesh Volume TYPE 8021 BOITe 0.800000 0.800000 9.93 VOLUME 8021 802 8021 13 4.467100 -7.200000 88.335

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* * Rods and sheaths in the principal mesh TYPE 8022 CYLZ 0.474623 9.93 VOLUME 8022 8021 8022 12 4.467100 -7.200000 88.335 TYPE 8023 CYLZ 0.418 9.93 VOLUME 8023 8022 8023 11 4.467100 -7.200000 88.335 TYPE 8024 CYLZ 0.394595 9.93 VOLUME 8024 8023 8024 10 4.467100 -7.200000 88.335 * * LATTICE's Parameters RESC MPRI 8021 DIMR 10 10 1 INDP 1 1 1 FINR * FINM * * * * MODU 8 * * External lattice's Volume TYPE 803 BOIT 8 8 9.93 VOLUME 803 0 803 13 0 -11.6671 88.335 * * Lattice's principal mesh Volume TYPE 8031 BOITe 0.800000 0.800000 9.93 VOLUME 8031 803 8031 13 -7.200000 -18.867100 88.33 5 * * Rods and sheaths in the principal mesh TYPE 8032 CYLZ 0.474623 9.93 VOLUME 8032 8031 8032 12 -7.200000 -18.867100 88.3 35 TYPE 8033 CYLZ 0.418 9.93 VOLUME 8033 8032 8033 11 -7.200000 -18.867100 88.3 35 TYPE 8034 CYLZ 0.394595 9.93 VOLUME 8034 8033 8034 10 -7.200000 -18.867100 88.3 35 * * LATTICE's Parameters RESC MPRI 8031 DIMR 10 10 1 INDP 1 1 1 FINR * FINM * * * *

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MODU 9 * * External lattice's Volume TYPE 804 BOIT 8 8 9.93 VOLUME 804 0 804 13 0 11.6671 88.335 * * Lattice's principal mesh Volume TYPE 8041 BOITe 0.800000 0.800000 9.93 VOLUME 8041 804 8041 13 -7.200000 4.467100 88.335 * * Rods and sheaths in the principal mesh TYPE 8042 CYLZ 0.474623 9.93 VOLUME 8042 8041 8042 12 -7.200000 4.467100 88.335 TYPE 8043 CYLZ 0.418 9.93 VOLUME 8043 8042 8043 11 -7.200000 4.467100 88.335 TYPE 8044 CYLZ 0.394595 9.93 VOLUME 8044 8043 8044 10 -7.200000 4.467100 88.335 * * LATTICE's Parameters RESC MPRI 8041 DIMR 10 10 1 INDP 1 1 1 FINR * FINM * * FING * * * SORTies SCORes ANNUle EXCEpt 3 CARA_REDUIT CARA_ETENDU CARA_ICSBEP FSCOres FSORties * SOURces UNIF 1 MODU 3 FINU UNIF 1 MODU 2 FINU UNIF 1 MODU 5 FINU UNIF 1 MODU 4 FINU UNIF 1 MODU 7 FINU UNIF 1 MODU 6 FINU UNIF 1 MODU 9 FINU UNIF 1 MODU 8 FINU FINSOURces * * *SIMU *DEBU 200

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*FSIM FIND * FIN_MORET

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APPENDIX B: UO2 FUEL RODS: CALCULATIONS OF THE DENSITY AND ITS ASSOCIATED UNCERTAINTY

The mean fuel density is obtained by considering:

• The mean linear mass density calculated on 1261 rods, ML = Linear Mass density: 5.0778 ± 0.0282 (1σ) g/cm

• The mean pellet diameter calculated on 53 pellets; D = diameter: 0.78919 ± 0.00176 (1σ) cm.

4/2D

ML

πρ = = 10.38 g/cm3.

The standard density uncertainty is obtained by combining the standard uncertainties of two measurements, x and y, the first one being ML and the second D:

Z = f(x,y).

( )yxy

Z

x

Z

y

Z

x

ZyxZ ,cov22

2

22

2

∂∂×

∂∂+

∂∂+

∂∂= σσσ .

The correlation coefficient is r = cov(x,y)/σxσy, r is equal to 0, because the linear mass density and the diameter were measured independently, therefore:

2

2

3

2

2

2

2 84DML D

MLD

σπ

σπ

σ ρ

+

= .

Hence, σρ = 0.073, that is to say 3σρ = 0.219 ≈ 0.22 g/cm3.

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APPENDIX C: CYLINDRIZATION OF THE PLUGS AND HOMOGENIZATION OF MATERIALS

Cylindrization of the Plugs As can be seen in Figure C-1 below, the shape of fuel-rod end plugs is quite complex. As a consequence, the lower and upper plugs have been simplified for the convenience of the benchmark-model users. The rods have been modelled into cylinders using two different methods for the two plugs:

• The lower plug is cylindrized, keeping the total mass constant (total mass = plug mass + clad mass in the zone); the equivalent plug height is derived from the following formula:

cmmassCladmassPlug

Hplug

Zr

plug 18.1

4

2=

××

+=φπ

ρ.

The simplification does not have a significant impact on reactivity since the total mass is kept constant.

• The upper plug is cylindrized, keeping the total length constant and the density constant. This does not have a significant impact on reactivity since the upper plug does not contribute significantly to total reactivity.

Therefore the rod length becomes 102.082-1.8+1.18 = 101.462 cm.

Table C-1: Characteristics of the true plugs.

Height (cm)

Diameter (cm)

Weight (g)

Value Value Value

Upper Plug 1.468 0.9492 3.4675 Rods

Lower Plug 1.8 0.9492 4.6321

Clad (Lower Plug) 0.8 cm 0.9492 – 0.836 0.8317

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Figure C-1: Sketch of the plugs (lower and upper, respectively).

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Homogenization of Materials The modelling process for cross sections in APOLLO2-MORET 4 requires homogenized materials. The homogenized materials are water (W), Zircaloy-4, or Zr4, for fuel cladding [Plug (P), Clad (C)], AG3 Grid (G), and air (A). Mixture zones are identified by the combination of these initials. The major geometrical values used in the homogenizations are in Table C-2.

Table C-2: Major geometrical values used in homogenizations.

Geometrical Dimension Notation Nominal Value (cm)

Array Pitch p 1.6

Fuel Clad Internal Diameter øint clad 0.836

Fuel Clad External Diameter øext clad 0.949245

AG3 Grid Holes Diameter øholes 0.98

Plug Diameter øplug_cyl 0.949245

The springs were not proposed in the benchmark definition (Section 3). Therefore, they are not retained in APOLLO2-MORET 4 homogenization calculations. The spring impact on reactivity worth is negligible. Lower zones in water There are two zones under water: the water-plug (WP) mixture and the water-plug-grid (WPG) mixture. Water Plug (WP Mixture : Bottom Plug) This zone is located between levels -1.18 cm and -0.4 cm, relative to the bottom of the UO2

WPcellhpV ×= 2 .

WP

cylplug

ZrhV ×=

4

2

4

π .

4ZrcellwaterVVV −= .

The results of calculation are reported in Table C-3

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Table C-3: Volume fractions in WP mixture.

Element Volume Fractions %

Zr4 (Plug) 27.64

Water 72.36

Water-Plug-Grid (WPG Mixture : Lower Grid) The grid is 0.4 cm thick with holes of 0.98 cm diameter. This zone is located between the levels -0.4 cm and 0 cm.

WPGcell hpV ×= 2

.

WPG

cylplug

ZrhV ×=

4

2

4

π .

WPGholes

WPGMAG hhpV4

22

3

φπ−×=.

43 ZrMAGcellwater VVVV −−= .

The results of calculation are reported in Table C-4.

Table C-4: Volume fractions in WPG mixture.

Element Volume Fractions

%

Zr4 (Plug) 27.64

AG3 (Grid) 70.54

Water 1.82

Intermediate Zones : Fissile Column This zone is located between the levels 0 cm and 89.765 cm. There are two different zones: fissile rods in water (0 cm to critical height) and fissile rods in air (critical height to 89.765 cm). Upper Zones in Air There are three zones in air: air-clad (AC) mixture, air-grid-clad (AGC) mixture, air-plug (AP) mixture. Air-Clad (AC Mixture) This zone is located between the heights 89.765 cm and 98.814 cm (height = 9.049 cm). It includes clad and air without spring. The clad is homogenized with air.

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ACScellhpV ×= 2 .

ACS

cladcladext

cladZrhVV

4

22

4

int__φφ

π−

== .

4Zrcellair VVV −= .

The results of calculation are reported in Table C-5.

Table C-5: Volume fractions in AC mixture.

Element Volume Fractions

Zr4 (Clad) 6.20%

Air 93.80%

Air-Grid-Clad (AGC Mixture) The grid is 0.4 cm thick with holes of 0.98 cm of diameter. This zone is located between the heights 97.5 cm and 97.9 cm for large and thin screen configurations and is located between 97.3 cm and 97.7 cm for reflexion screen configuration.

AGCS2

cell hpV ×= .

AGCScladcladext

Zr hV4

2int_

2_

4

φφπ

−= .

AGCS

holes

AGCSMAGhhpV

4

2

2

3

φπ−×= .

43 ZrAGcellair VVVV −−= .

The results of calculation are reported in Table C-6.

Table C-6: Volume fractions in AGCS mixture.

Element Volume Fractions %

Zr4 (Clad) 6.20

AG3 (Grid) 70.54

Air 23.26

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Air-Plug (AP Mixture – Top Plug) This zone is located between the heights 98.814 cm and 100.282 cm (height = 1.468 cm). It includes the cylindrized top plug.

APcell hpV ×= 2

.

AP

cylplug

ZrhV ×=

4

2

4

π .

4ZrcellairVVV −= .

The results of the calculation are reported in Table C-7.

Table C-7: Volume fractions in AP mixture.

Element Volume Fractions %

Zr4 (Plug) 27.64

Air 72.36

Lower and upper grids without rods . The grids are 0.4 cm thick with holes of 0.98-cm diameter.

GridCell hpV ×= 2 .

GridcylHole

Hole hV ×=4

2_φ

π .

HoleCellGrid VVV −= .

The results of the calculation are reported in Table C-8.

Table C-8: Volume fractions in AP mixture.

Element Volume Fractions

%

AG3 (Grid) 70.54

Air or Water (Holes) 29.46

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Five zones of small reactivity worth could be described with homogenized materials according to percentages given in Table C-3 to C-9. The corresponding atom densities are given in Table C-10, Table C-11, and Table C-12.

Table C-9: Volume percentages of homogenized zones.

Zones Volume

Percentages (%)

Plug (Zircaloy-4) 27.64 Bottom Plug

Water 72.36

Plug (Zircaloy-4) 27.64

Grid (AG3 ) 70.54 With rods

Water 1.82

Grid (AG3) 70.54

Lower Grid

Without rods Water 29.46

Plug (Zircaloy-4) 27.64 Top Plug

Air 72.36

Clad (Zircaloy-4) 6.20

Grid (AG3 ) 70.54 With rods

Air 23.26

Grid (AG3) 70.54

Upper Grid

Without rods Water 29.46

Clad (Zircaloy-4) 6.20 Spring Zone

Air 93.80

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Table C-10: Atom densities for homogenized zones (atom/barn-cm).

ZONE Element Atom Densities (atom/barn-cm)

H 2.4019E-02

O 9.4434E-05

Al 7.9411E-07

Fe 4.3904E-05 Si 3.8932E-06 N 2.4444E-06 Sn 1.2709E-04 Cr 2.5065E-05 C 1.1825E-05 Hf 3.4404E-07 H 4.0543E-06

Bottom Plug (Plug + Water)

Zr 1.1880E-02

Si 1.6530E-04

Fe 1.2467E-04 Cu 1.7839E-05 Mn 1.0317E-04

Mg 1.6790E-03

Cr 9.0226E-05

Zn 3.5463E-05 Ti 3.5513E-05

Al 3.9640E-02

N 2.4208E-06 O 9.3524E-05 Sn 1.2586E-04 C 1.1711E-05 Zr 1.1765E-02 Hf 3.4072E-07 H 4.0152E-06

Lower Grid (Plug + Water +Grid)

H2O 5.9049E-04 N 3.2674E-05 O 1.0254E-04 Sn 1.2709E-04 Fe 4.3904E-05 Cr 2.5065E-05 C 1.1825E-05 Si 3.8932E-06 Zr 1.1880E-02 Al 7.9411E-07 Hf 3.4404E-07

Top Plug (Plug + Air)

H 4.0543E-06

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Table C-11: Atom densities for homogenized zones (atom/barn-cm).

ZONE Element Atom Densities (atom/barn-cm)

Si 1.6239E-04 Fe 9.0957E-05 Cu 1.7848E-05 Mn 1.0322E-04 Mg 1.6799E-03 Cr 7.0988E-05 Zn 3.5481E-05 Ti 3.5531E-05 Al 3.9659E-02 N 1.0308E-05 O 2.3539E-05 H 8.9810E-07 Hf 7.6211E-08 C 2.6195E-06 Zr 2.6316E-03

Upper Grid (Grid + Clad + Air)

Sn 2.8153E-05 Cr 5.5522E-06 H 8.9810E-07 Hf 7.6211E-08 O 3.1483E-05 Si 8.6240E-07 Fe 9.7255E-06 N 3.9922E-05 C 2.6195E-06 Zr 2.6316E-03 Al 1.7591E-07

Spring Zone (Clad + Air)

Sn 2.8153E-05

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Table C-12: Atom densities for homogenized zones (atom/barn-cm)

ZONE Element Atom Densities (atom/barn-cm)

Si 1.6145E-04

Fe 8.1191E-05

Cu 1.7839E-05

Mn 1.0317E-04

Mg 1.6790E-03

Cr 6.5403E-05

Zn 3.5463E-05

Ti 3.5513E-05

Al 3.9639E-02

H 1.9682E-02

Lower Grids without holes (AG3 + H2O)

O 9.8411E-03

Si 1.6145E-04

Fe 8.1191E-05

Cu 1.7839E-05

Mn 1.0317E-04

Mg 1.6790E-03

Cr 6.5403E-05

Zn 3.5463E-05

Ti 3.5513E-05

Al 3.9639E-02

N 1.2386E-05

Upper Grids without holes (AG3 + Air)

O 3.3226E-06

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APPENDIX D: COMPARISON WITH MORET 5 CODE (UNDER VALIDATION AT IRSN) MONTE CARLO CONTINUOUS ENERGY

CODE

The APOLLO2-MORET 4 calculations using the correlated sampling method were compared to two APOLLO2-MORET 4 direct calculations with a low Monte Carlo standard deviation; the purpose was to validate the correlated sampling method. In a second step, the APOLLO2-MORET 4 calculations were compared to MORET 5 calculations to validate the cell calculations and the different physical assumptions and models in APOLLO2 code. The results in Table D-1 show that a general good agreement is obtained between codes.

Table D-1: 4A-Ti-005 – Case 1.

Parameter Identification Parameter

Variation in Calculation

APOLLO2-MORET 4 172-energy groups

Correlated sampling ∆keff × 105555

JEF2.2 library

APOLLO2-MORET 4 172-energy groups Direct calculations

(σσσσ = 0.00010) ∆keff × 105555

JEF2.2 library

MORET 5 continuous energy Direct calculations

(σσσσ = 0.00010) ∆keff × 105555

JEF2.2 library

Density (g/cm3) ±0.073 220 255 228

Water Density (g/cm3) ±0.1% 53 77 63

Fuel Pellet Diameter (mm) ±0.1 27 4 22

Clad Outer Diameter systematic (mm)

±0.005 19 16 18

Critical water height (mm) ±6 -- 150 126

Sructural material thickness (mm)

±0.12 -- 210 227

Screen density (g/cm3) ±0.05 79 76 108

Position of rod arrays (mm)

+1 -- 117 147

Subtotal -- -- 397 397

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APPENDIX E: NEUTRON COUNTERS POSITION AND NEUTRON SOURCES

The neutron counters and neutron sources positions are presented in this appendix. The data come from the logbooks. H is the distance between the bottom of the fissile column and the level of the neutron counters. D is the distance between the core periphery and the neutron counters.

Figure E-1: 4A-Ti-005.

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Figure E-2: 4A-Ti-010.

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APPENDIX F: GLOW DISCHARGE MASS SPECTROMETRY TECHNIQUE (GDMS)

A description a the GDMS technique, as well as trhe results of titanium screens measurements are provided below.

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APPENDIX G: MEASUREMENT OF TITANIUM SCREENS WITH A MICROMETER

In this appendix, the measurements performed with the micrometer device are provided for the 4A-Ti-005 and 4A-Ti-010 experiments. The points’ positions are shown in Figure 16.

Measurement of the groove Measurement of the

thickness

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Measurement of the groove

Measurement of the thickness

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Measurement of the groove

Measurement of the thickness

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Measurement of the groove

Measurement of the thickness

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APPENDIX H: PLANS OF THE BASKET AND THE GRID

Different cross cuts of the basket are given in this appendix along with a plan of the grids.

Figure H-1. Caption.

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Figure H-2. Caption.

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Figure H-3. Caption.

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Figure H-4. Caption.

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APPENDIX I: DESCRIPTION OF THE WEDGES FOR REFERENCE EXPERIMENTS

A description of wedges (lower and upper part) used in the reference experiments (material replaced by water) is provided with in this appendix in Figure I-1 to I-2.

Figure I-1: R4A-Eau-003, R4A-Eau-005, R4A-Eau-010 and R4A-Eau-020 – upper part.

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Figure I-2: R4A-Eau-003, R4A-Eau-005, R4A-Eau-010 and R4A-Eau-020 – lower part.

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APPENDIX J: RODS RECLADDING

Height and mass of rods

In 1995, 1299 AGS clad fuel rods were sent by the Valduc criticality laboratory to FBFC/Pierrelatte to be reclad in zircaloy. Following this operation, the 1261 reclad rods were redirected to Valduc, as well as 17,723 g of oxide corresponding to the discarded pellets. This has been the subject of the draft report; the final report has not been published. The draft report includes results of the following measurements:

• The length of the unclad rod fissile column • The length and mass of the fissile column before recladding.

Mr. Laplace of Valduc criticality laboratory attended this operation in Pierrelatte. Hereafter is the description he made in 2000 based on his memories. “The rods were removed one by one. Once removed from the the AGS cladding, the column of pellets was placed in a dedicated device (chute) for the purpose of visual inspection. The pellets with chips were then removed and replaced with unbroken pellets coming from another rod. The column thus reconstituted, of about 90 cm length, was then introduced into the zircaloy cladding welded by a zircaloy plug at its bottom . The spring was then introduced and the second plug was then welded.” The following measurements were then made (designation for the parameter in below table):

• Rod length (Lcc) • Fissile column length after recladding (1242 rods) (Lc2) • Fissile column length reconstituted before recladding (1261 rods) (Lc1) • Weight: tube + bottom plug (zircaloy) (Weight TSBI or Pbi) • Weight: tube + bottom plug (zircaloy) + fissile column restored (Weight TSBI + uranium

or Pc). The weight of the reconstructed fissile column is obtained by difference between Pc and Pbi. Results of the measurements are reported in Table J-1. The rods are categorized as follows, in accordance with their quality:

• 1238 rods of Category 1 • 4 + 1 (No. 959) repaired rods of Category 1 (welding needed to repair the rod) • 19 rods of Category 2 filled with pellets of Class B.

Mr. Laplace reported that the surface of the pellets was flat. The dimensions of rods retained for Valduc programs (including MIRTE program) are based on the measurements of the 1261 rods including repaired rods and those of Category 2.

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Table J-1: Results of rods measurements.

Rods of category 1 Rod Number Fissile column

length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g)

1 894.44 895.87 1020.86 1.43 567 111 456

2 899.38 896.21 1021.03 -3.17 567 111 456

3 898.48 899.46 1020.98 0.98 567 110 457

4 898.62 899.16 1020.56 0.54 570 110 460

5 894.74 896.28 1020.64 1.54 565 110 455

6 896.26 897.59 1021.01 1.33 567 111 456

7 898.62 898.28 1020.33 -0.34 568 110 458

8 896.54 898.20 1020.61 1.66 566 109 457

9 895.06 893.70 1020.91 -1.36 564 109 455

10 897.41 898.17 1020.53 0.76 567 109 458

11 899.52 900.89 1020.56 1.37 568 111 457

12 895.47 896.64 1020.79 1.17 562 110 452

13 901.61 903.25 1020.95 1.64 570 110 460

14 895.75 897.94 1020.86 2.19 566 110 456

15 898.91 899.36 1020.97 0.45 566 110 456

16 899.36 899.40 1020.99 0.04 568 109 459

17 884.36 882.57 1020.78 -1.79 557 108 449

18 898.91 898.25 1020.89 -0.66 568 110 458

19 899.90 896.36 1020.87 -3.54 564 110 454

20 898.49 899.37 1020.80 0.88 567 110 457

21 896.36 897.79 1020.86 1.43 565 109 456

22 894.20 893.35 1020.95 -0.85 565 110 455

23 892.84 894.61 1020.70 1.77 563 109 454

24 895.88 897.01 1020.34 1.13 566 110 456

25 899.96 900.72 1020.66 0.76 567 109 458

26 894.84 895.51 1020.93 0.67 565 109 456

27 897.18 897.67 1020.78 0.49 568 110 458

28 897.71 899.58 1020.56 1.87 567 109 458

29 895.24 897.46 1020.93 2.22 564 109 455

30 898.58 899.9 1020.95 1.32 567 111 456

31 900.85 899.39 1021.00 -1.46 566 109 457

32 899.11 898.80 1020.59 -0.31 566 109 457

33 899.01 899.12 1021.04 0.11 567 110 457

34 895.1 896.76 1020.94 1.66 567 111 456

35 898.75 899.73 1020.79 0.98 569 111 458

36 897.22 897.51 1020.94 0.29 568 110 458

37 894.50 895.22 1020.54 0.72 566 110 456

38 898.14 898.52 1020.83 0.38 568 110 458

39 896.93 898.65 1020.94 1.72 566 110 456

40 897.81 899.17 1020.93 1.36 568 110 458

41 895.15 896.71 1021.02 1.56 567 111 456

42 898.37 898.7 1021.12 0.33 567 110 457

43 898.15 898.82 1020.83 0.67 566 109 457

44 899.51 900.9 1021.06 1.39 567 110 457

45 895.5 897.6 1021.03 2.10 566 111 455

46 897.94 900.01 1020.87 2.07 565 108 457

47 896.93 898.08 1020.89 1.15 568 110 458

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Table J-1: Results of rods measurements (continued). Rods of Category 1

Rod Number

Fissile column length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g) 48 903.03 899.65 1021.05 -3.38 567 110 457 49 898.42 898.36 1021.06 -0.06 567 109 458 50 897.68 898.73 1021.04 1.05 564 109 455 51 898.95 899.64 1020.76 0.69 568 110 458 52 899.21 899.52 1020.78 0.31 567 110 457 53 896.60 897.18 1020.51 0.58 567 110 457 54 896.37 898.95 1020.83 2.58 567 110 457 55 895.44 896.02 1020.78 0.58 567 109 458 56 898.00 898.17 1020.55 0.17 568 110 458 57 896.34 897.39 1020.39 1.05 565 111 454 58 895.26 896.46 1020.50 1.20 565 110 455 59 897.40 898.06 1020.55 0.66 565 110 455 60 893.94 894.54 1020.84 0.60 565 110 455 61 897.19 896.86 1020.70 -0.33 565 110 455 62 894.58 895.35 1020.85 0.77 566 110 456 63 896.45 897.92 1020.78 1.47 566 109 457 64 893.63 895.31 1020.85 1.68 564 110 454 65 899.48 900.53 1020.67 1.05 568 110 458 66 894.40 896.31 1020.56 1.91 568 110 458 67 897.90 898.70 1020.85 0.80 567 110 457 68 894.55 895.09 1020.97 0.54 567 110 457 69 896.31 896.91 1020.83 0.60 564 110 454 70 894.24 894.46 1020.73 0.22 564 110 454 71 895.46 896.61 1020.52 1.15 567 110 457 72 894.43 895.19 1020.43 0.76 566 110 456 73 898.12 898.95 1020.57 0.83 568 110 458 74 896.34 893.99 1020.77 -2.35 565 110 455 75 897.72 899.41 1020.78 1.69 569 111 458 76 897.67 898.16 1021.02 0.49 567 110 457 77 900.79 900.09 1021.01 -0.70 565 110 455 78 899.28 898.92 1020.88 -0.36 566 111 455 79 894.04 895.5 1020.90 1.46 566 110 456 80 901.62 899.97 1021.14 -1.65 568 109 459 81 899.22 898.93 1020.40 -0.29 568 111 457 82 899.45 898.39 1021.03 -1.06 566 110 456 83 894.40 895.19 1021.04 0.79 563 110 453 84 895.93 896.00 1020.88 0.07 565 110 455 85 898.49 899.47 1020.72 0.98 567 111 456 86 891.21 893.42 1020.90 2.21 562 109 453 87 899.57 901.72 1020.91 2.15 569 111 458 88 899.22 899.38 1020.64 0.16 567 111 456 89 897.59 897.06 1020.85 -0.53 565 110 455 90 893.92 894.87 1020.74 0.95 565 109 456 91 895.34 895.89 1020.86 0.55 565 110 455 92 896.96 898.01 1020.60 1.05 567 110 457 93 895.06 895.88 1020.89 0.82 565 109 456 94 900.59 902.82 1020.90 2.23 569 110 459 95 896.62 896.08 1020.67 -0.54 567 110 457 96 897.15 898.53 1020.51 1.38 564 109 455 97 897.09 897.14 1020.99 0.05 566 109 457

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Table J-1: Results of rods measurements (continued). Rod Number Fissile column

length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g)

98 897.69 897.51 1020.71 -0.18 567 110 457

99 894.66 895.49 1020.84 0.83 567 110 457

100 894.94 895.49 1020.89 0.55 563 110 453

101 894.08 893.46 1021.13 -0.62 566 110 456

102 897.82 898.93 1020.74 1.11 568 110 458

103 897.89 899.01 1020.77 1.12 568 110 458

104 898.41 898.54 1020.33 0.13 568 110 458

105 897.84 898.78 1020.60 0.94 566 110 456

106 894.62 894.96 1020.87 0.34 565 110 455

108 896.92 898.21 1020.45 1.29 566 110 456

109 897.77 901.74 1021.01 3.97 567 110 457

110 893.89 892.23 1020.55 -1.66 571 110 461

111 903.27 899.05 1021.11 -4.22 568 110 458

112 898.02 896.00 1021.00 -2.02 566 110 456

113 893.75 894.53 1020.81 0.78 566 110 456

114 897.30 898.24 1020.54 0.94 566 110 456

115 897.66 899.74 1020.25 2.08 567 110 457

116 895.78 896.25 1020.70 0.47 567 110 457

117 898.82 897.64 1020.98 -1.18 567 111 456

118 895.46 895.29 1020.82 -0.17 565 110 455

119 896.16 897.39 1020.90 1.23 567 111 456

120 897.38 898.28 1020.59 0.90 564 110 454

121 892.06 893.69 1021.08 1.63 564 110 454

122 896.06 896.38 1020.94 0.32 568 110 458

123 896.08 897.03 1020.90 0.95 564 110 454

124 898.9 899.73 1020.91 0.83 568 110 458

125 894.68 894.08 1021.05 -0.60 563 110 453

126 896.85 897.24 1021.12 0.39 565 108 457

127 896.84 897.34 1020.31 0.50 568 109 459

128 898.05 899.52 1020.77 1.47 569 110 459

129 892.96 895.82 1020.65 2.86 565 110 455

130 899.18 900.78 1020.47 1.60 566 109 457

131 896.90 897.25 1020.59 0.35 566 109 457

132 899.45 899.72 1020.81 0.27 567 110 457

133 895.28 897.63 1020.36 2.35 567 110 457

134 897.74 897.75 1020.53 0.01 568 110 458

135 895.73 897.59 1020.52 1.86 567 110 457

136 896.35 897.30 1020.96 0.95 566 109 457

137 898.63 899.25 1021.02 0.62 567 110 457

138 898.15 899.02 1020.66 0.87 568 111 457

139 894.32 896.84 1020.80 2.52 563 110 453

140 890.5 891.64 1021.01 1.14 562 110 452

141 902.32 901.03 1020.68 -1.29 567 110 457

142 896.78 897.64 1020.54 0.86 567 110 457

143 895.47 895.64 1020.87 0.17 562 110 452

144 896.93 897.39 1020.74 0.46 566 109 457

145 897.1 897.56 1021.06 0.46 566 110 456

146 897.50 899.20 1020.54 1.70 566 110 456

147 895.23 896.42 1020.99 1.19 566 110 456

148 900.03 901.48 1020.49 1.45 570 111 459

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Table J-1: Results of rods measurements (continued). Rod

Number Fissile column length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g)

149 895.48 896.00 1020.57 0.52 565 109 456 150 891.52 892.72 1021.70 1.20 563 109 454 151 891.90 892.51 1020.63 0.61 564 110 454 152 900.26 900.85 1021.04 0.59 566 109 457 153 897.92 898.59 1020.34 0.67 566 110 456 154 894.87 893.41 1020.77 -1.46 564 110 454 155 896.76 897.09 1020.96 0.33 566 109 457 156 897.81 898.64 1020.50 0.83 567 109 458 157 898.48 899.02 1021.02 0.54 569 110 459 158 895.23 896.98 1021.04 1.75 565 109 456 159 894.36 895.53 1020.52 1.17 564 110 454 160 895.76 897.12 1020.60 1.36 565 110 455 161 891.10 891.65 1021.08 0.55 563 111 452 162 892.02 891.47 1020.79 -0.55 562 110 452 163 895.25 896.00 1020.96 0.75 562 109 453 164 895.55 896.14 1020.40 0.59 566 109 457 165 902.64 898.94 1020.81 -3.70 561 110 451 166 901.73 898.89 1021.07 -2.84 567 110 457 167 897.88 898.81 1021.09 0.93 567 110 457 168 895.66 896.06 1020.92 0.40 567 109 458 169 898.94 899.54 1020.50 0.60 566 110 456 170 894.97 893.54 1020.84 -1.43 566 110 456 171 893.60 893.81 1020.72 0.21 563 110 453 172 896.82 896.93 1020.97 0.11 566 109 457 173 895.53 896.19 1020.84 0.66 566 109 457 174 898.70 899.21 1020.83 0.51 567 110 457 175 901.29 899.26 1020.86 -2.03 565 110 455 176 898.11 898.53 1020.71 0.42 565 109 456 177 894.41 895.42 1020.92 1.01 564 110 454 178 894.65 895.98 1020.61 1.29 565 110 455 179 893.95 899.36 1020.96 5.41 564 109 455 180 899.56 900.06 1020.92 0.50 566 109 457 181 897.06 898.28 1020.67 1.22 567 109 458 182 899.83 900.45 1020.81 0.62 568 110 458 183 898.61 899.61 1020.63 1.00 568 110 458 184 898.73 899.29 1021.07 1.29 568 110 458 185 897.61 899.85 1021.03 2.24 566 110 456 187 900.15 901.05 1020.60 0.90 570 111 459 188 894.14 894.75 1020.83 1.29 565 110 455 189 897.24 897.97 1020.95 1.29 567 110 457 190 899.56 899.95 1021.06 1.29 568 110 458 191 898.39 896.94 1020.85 1.29 563 110 453 192 897.44 897.92 1020.69 1.29 565 109 456 193 897.56 897.18 1021.03 1.29 565 109 456 194 898.28 898.97 1020.70 1.29 567 110 457 195 898.22 897.98 1021.12 1.29 567 110 457 196 892.19 892.39 1020.79 0.20 563 110 453 197 896.34 896.57 1020.64 0.23 565 110 455 198 898.92 896.51 1020.98 -2.41 566 110 456 199 894.48 899.18 1021.06 4.70 566 110 456

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Table J-1: Results of rods measurements (continued). Rod

Number Fissile column length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g)

200 899.07 899.78 1020.77 0.71 568 110 458 201 899.97 900.66 1021.13 0.69 568 110 458 202 892.96 895.64 1020.55 2.68 561 109 452 203 897.41 897.82 1020.57 0.41 566 110 456 204 897.99 899.16 1020.95 1.17 567 110 457 205 896.17 899.85 1020.69 3.68 566 110 456 206 894.46 896.05 1020.79 1.59 563 109 454 207 900.13 900.92 1021.19 0.79 568 109 459 208 897.51 899.54 1020.83 1.29 566 109 457 209 896.39 898.55 1020.59 2.16 565 109 456 210 892.26 892.93 1020.98 0.67 564 110 454 211 898.73 900.43 1021.04 1.29 567 110 457 212 899.06 899.27 1020.80 0.21 568 110 458 213 896.83 898.12 1020.93 1.29 566 111 455 214 897.97 898.68 1021.09 0.71 566 109 457 215 897.72 899.69 1020.92 1.97 561 110 451 216 899.09 899.72 1020.88 0.63 568 110 458 217 901.44 902.89 1021.17 1.45 565 110 455 218 898.05 899.03 1020.96 0.98 566 110 456 219 896.96 897.38 1020.60 0.42 563 110 453 220 898.34 894.89 1020.96 -3.45 566 111 455 221 894.02 894.68 1021.02 0.66 561 110 451 222 896.41 898.55 1020.83 2.14 565 109 456 223 899.06 899.31 1020.82 0.25 565 109 456 224 899.46 899.45 1020.83 -0.01 568 110 458 225 896.83 897.58 1021.18 0.75 565 109 456 226 895.82 896.31 1020.67 0.49 566 110 456 227 898.14 899.17 1020.89 1.03 566 109 457 228 897.86 896.53 1020.74 -1.33 564 110 454 229 896.64 895.99 1020.90 -0.65 565 109 456 230 902.15 900.46 1020.89 -1.69 567 111 456 231 898.07 898.95 1020.71 0.88 566 110 456 232 900.17 900.90 1020.53 0.73 567 110 457 233 898.59 899.31 1021.04 0.72 567 110 457 234 899.01 898.55 1021.00 -0.46 564 110 454 235 900.91 901.35 1020.76 0.44 566 109 457 236 898.83 899.39 1020.67 0.56 565 109 456 237 893.68 892.14 1021.00 -1.54 565 109 456 238 899.00 899.62 1020.84 0.62 568 110 458 240 894.09 895.67 1020.97 1.58 566 109 457 241 892.52 892.89 1020.51 0.37 564 110 454 242 898.80 899.73 1020.71 0.93 567 110 457 243 892.42 893.68 1020.48 1.26 563 110 453 244 899.24 900.51 1020.59 1.27 565 110 455 245 896.24 896.61 1020.93 0.37 567 110 457 246 898.38 898.50 1021.06 0.12 565 109 456 247 897.26 898.71 1020.93 1.45 567 110 457 248 896.87 897.16 1020.90 0.29 564 110 454 249 898.19 898.68 1020.96 0.49 563 110 453 250 898.75 899.18 1020.95 0.43 568 109 459

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Table J-1: Results of rods measurements (continued). Rod

Number Fissile column length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g)

251 898.15 898.71 1020.57 0.56 566 110 456 252 893.99 894.16 1020.49 0.17 562 110 452 253 899.80 899.29 1020.96 -0.51 566 110 456 254 894.62 895.60 1020.92 0.98 563 110 453 255 894.41 895.05 1020.91 0.64 565 110 455 256 897.50 898.59 1021.04 1.09 568 111 457 257 898.34 899.25 1020.50 0.91 566 109 457 258 900.54 898.31 1020.96 -2.23 565 110 455 259 897.19 897.93 1020.76 0.74 566 110 456 260 897.77 898.41 1020.92 0.64 565 110 455 261 891.00 891.06 1020.51 0.06 561 109 452 262 897.93 899.00 1020.88 1.07 567 109 458 263 897.03 898.08 1021.01 1.05 569 110 459 264 897.35 897.97 1020.98 0.62 567 110 457 265 898.76 899.71 1020.92 0.95 567 110 457 266 896.14 896.97 1021.02 0.83 567 110 457 267 892.42 894.78 1020.77 2.36 560 110 450 268 899.06 903.40 1020.82 4.34 563 110 453 269 899.34 897.06 1020.91 -2.28 565 110 455 270 899.90 900.26 1020.95 0.36 568 111 457 272 895.82 898.45 1020.75 2.63 565 110 455 273 899.97 899.98 1020.96 0.01 568 109 459 274 896.52 897.88 1020.97 1.36 566 111 455 275 897.75 898.65 1020.83 0.90 566 110 456 276 901.61 902.16 1020.71 0.55 557 110 447 277 892.43 893.27 1020.87 0.84 561 111 450 278 899.49 898.32 1020.56 -1.17 566 111 455 279 898.81 900.51 1020.74 1.70 566 110 456 280 898.22 898.59 1020.89 0.37 567 111 456 281 894.35 895.37 1020.54 1.02 565 110 455 282 892.48 891.56 1021.10 -0.92 563 110 453 283 901.08 903.16 1020.63 2.08 568 110 458 284 901.46 898.28 1020.67 -3.18 567 111 456 285 896.33 897.23 1020.76 0.90 566 110 456 286 895.07 895.45 1020.69 0.38 566 110 456 287 898.75 901.86 1020.88 3.11 567 109 458 288 896.65 896.61 1020.82 -0.04 567 110 457 289 895.00 896.99 1021.10 1.99 564 110 454 290 900.13 901.30 1020.78 1.17 565 110 455 291 904.45 897.10 1021.06 -7.35 563 110 453 292 890.76 891.73 1020.65 0.97 560 110 450 293 899.76 900.25 1020.72 0.49 569 110 459 294 897.81 898.32 1021.04 0.51 564 108 456 295 896.88 897.16 1020.57 0.28 566 109 457 296 894.66 893.90 1020.90 -0.76 563 110 453 297 897.04 897.86 1020.54 0.82 567 110 457 298 902.96 902.07 1020.59 -0.89 569 110 459 299 899.46 899.82 1020.63 0.36 567 111 456 300 893.88 892.26 1020.87 -1.62 564 110 454 301 895.24 896.94 1021.04 1.70 567 110 457

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Table J-1: Results of rods measurements (continued). Rod

Number Fissile column length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g)

302 897.76 898.05 1020.92 0.29 565 110 455 303 895.51 895.87 1021.07 0.36 567 109 458 304 894.80 892.51 1020.98 -2.29 564 110 454 305 897.9 898.95 1020.61 1.05 567 109 458 306 898.77 899.87 1020.88 1.10 567 109 458 307 896.69 897.21 1020.92 0.52 566 109 457 308 897.71 898.29 1020.84 0.58 567 109 458 309 896.04 896.09 1020.93 0.05 564 110 454 310 894.28 894.85 1020.88 0.57 560 108 452 311 892.75 892.95 1021.04 0.20 561 109 452 312 895.37 895.69 1020.95 0.32 568 109 459 313 893.80 894.80 1020.84 1.00 565 110 455 314 895.00 895.78 1020.97 0.78 566 109 457 315 895.5 896.41 1021.17 0.91 566 109 457 316 897.09 897.05 1020.97 -0.04 564 109 455 317 900.85 900.43 1020.94 -0.42 565 109 456 318 895.61 896.17 1020.87 0.56 565 109 456 319 893.81 893.07 1021.03 -0.74 564 110 454 320 891.72 892.02 1020.66 0.30 564 110 454 321 894.17 896.73 1020.52 2.56 563 109 454 322 896.34 890.83 1020.86 -5.51 567 110 457 323 897.06 897.10 1021.12 0.04 567 110 457 324 894.89 896.22 1020.22 1.33 566 110 456 325 898.32 899.06 1020.65 0.74 568 110 458 326 896.04 898.82 1020.62 2.78 562 109 453 327 894.63 887.81 1021.01 -6.82 563 109 454 328 895.38 896.29 1021.12 0.91 566 109 457 329 892.39 893.43 1020.82 1.04 563 109 454 330 898.03 898.17 1020.53 0.14 564 110 454 331 892.91 893.27 1020.41 0.36 566 110 456 332 899.62 900.24 1021.19 0.62 568 108 460 335 898.16 896.36 1020.57 -1.80 563 109 454 336 897.90 898.01 1020.76 0.11 568 111 457 337 894.86 895.8 1020.95 0.94 566 109 457 338 897.69 897.76 1020.85 0.07 566 110 456 339 896.53 898.54 1020.48 2.01 565 110 455 340 897.1 897.44 1020.66 0.34 568 110 458 342 896.47 897.73 1020.83 1.26 567 110 457 343 896.93 897.30 1020.72 0.37 566 110 456 344 893.63 894.00 1021.14 0.37 566 111 455 345 899.9 899.29 1021.21 -0.61 569 110 459 346 901.87 899.22 1020.87 -2.65 565 109 456 347 894.59 894.89 1017.86 0.30 565 109 456 348 897.08 897.74 1020.75 0.66 568 109 459 349 898.29 898.87 1020.50 0.58 567 111 456 350 898.74 899.35 1020.74 0.61 569 109 460 352 898.91 899.11 1020.62 0.20 565 109 456 353 897.68 898.01 1020.90 0.33 565 110 455 354 893.32 893.07 1020.78 -0.25 565 110 455 356 897.08 898.21 1020.80 1.13 566 109 457

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Table J-1: Results of rods measurements (continued). Rod

Number Fissile column length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g)

360 896.94 898.3 1021.28 1.36 567 109 458 364 897.22 897.59 1020.80 0.37 565 109 456 365 900.62 900.51 1020.68 -0.11 567 110 457 367 897.93 898.31 1020.45 0.38 566 110 456 371 894.09 893.65 1020.95 -0.44 566 109 457 374 897.05 895.85 1020.93 -1.20 561 109 452 380 893.77 894.47 1020.78 0.70 565 110 455 382 899.83 900.68 1021.06 0.85 567 109 458 384 898.06 900.72 1021.01 2.66 566 110 456 385 898 899.05 1021.08 1.05 568 109 459 386 892.58 892.80 1020.67 0.22 563 110 453 388 899.38 899.84 1020.85 0.46 565 110 455 389 893.83 894.94 1021.04 1.11 565 109 456 391 894.94 897.56 1020.84 2.62 565 110 455 393 898.28 898.84 1020.89 0.56 568 110 458 394 898.61 900.07 1021.22 1.46 567 110 457 396 895.9 896.46 1021.07 0.56 567 111 456 397 898.33 899.81 1020.76 1.48 566 110 456 399 896.50 899.92 1020.98 3.42 566 109 457 400 897.79 900.00 1021.04 2.21 565 110 455 401 898.61 899.06 1021.10 0.45 566 110 456 402 898.6 899.87 1020.85 1.27 567 109 458 403 895.06 896.16 1020.88 1.10 567 110 457 404 895.38 896.45 1020.93 1.07 110 405 896.05 895.86 1020.85 -0.19 562 110 452 406 896.56 897.49 1020.92 0.93 566 110 456 407 895.79 895.98 1021.03 0.19 564 109 455 408 896.73 897.14 1021.02 0.41 565 110 455 409 897.34 898.03 1021.30 0.69 568 110 458 410 896.66 896.93 1020.65 0.27 566 109 457 411 895.84 894.17 1020.94 -1.67 564 110 454 412 895.41 898.29 1020.93 2.88 566 110 456 413 901.18 901.83 1021.02 0.65 569 110 459 414 896.35 895.30 1020.96 -1.05 564 109 455 415 893.94 894.7 1020.80 0.76 565 110 455 416 897.34 898.90 1020.99 1.56 568 110 458 417 900.32 898.11 1020.67 -2.21 568 110 458 418 897.88 898.56 1020.90 0.68 568 111 457 419 897.14 896.53 1020.86 -0.61 566 110 456 420 893.94 896.13 1020.77 2.19 567 110 457 421 898.62 898.84 1020.61 0.22 563 110 453 422 898.03 898.56 1020.91 0.53 566 109 457 423 896.05 897.42 1020.66 1.37 566 109 457 424 894.79 897.18 1020.70 2.39 546 109 437 425 897.91 897.18 1020.88 -0.73 565 109 456 426 899.39 901.63 1020.97 2.24 567 109 458 427 897.89 900.39 1020.95 2.50 568 110 458 428 895.46 896.51 1020.98 1.05 567 110 457 429 897.14 898.91 1020.65 1.77 567 110 457 430 895.93 897.61 1020.92 1.68 567 110 457

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Table J-1: Results of rods measurements (continued). Rod

Number Fissile column length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g)

431 897.61 900.59 1020.89 2.98 569 111 458 432 896.83 899.67 1020.76 2.84 567 111 456 433 897.52 897.97 1021.08 0.45 566 110 456 434 894.19 896.52 1021.00 2.33 566 109 457 435 895.94 898.29 1021.01 2.35 565 110 455 436 894.47 895.92 1020.73 1.45 564 109 455 437 898.31 900.92 1021.03 2.61 566 109 457 438 898.28 898.51 1021.00 0.23 110 439 896.81 898.07 1020.97 1.26 567 110 457 440 897.53 897.59 1020.93 0.06 565 110 455 441 898 899.39 1020.94 1.39 566 109 457 442 897.02 899.47 1020.56 2.45 569 109 460 443 895.46 894.43 1020.83 -1.03 565 110 455 444 898.13 899.98 1021.02 1.85 567 110 457 445 893.72 896.06 1020.87 2.34 564 110 454 446 895.34 896.63 1020.95 1.29 566 109 457 447 894.47 896.54 1020.90 2.07 566 110 456 448 896.31 898.77 1020.54 2.46 565 109 456 449 899.23 901.36 1020.91 2.13 568 109 459 450 893.7 894.97 1020.92 1.27 563 110 453 451 897.4 898.86 1021.17 1.46 565 109 456 452 893.04 893.12 1020.42 0.08 565 110 455 453 899.03 897.33 1020.45 -1.70 565 110 455 454 898.53 900.15 1021.15 1.62 566 110 456 455 893.37 895.67 1020.39 2.30 565 110 455 456 897.03 897.36 1020.57 0.33 566 110 456 457 895.68 898.94 1021.01 3.26 563 108 455 458 898 900.08 1020.66 2.08 565 110 455 460 897.96 899.25 1020.94 1.29 566 108 458 461 892.9 892.29 1021.03 -0.61 564 109 455 462 897.88 897.36 1021.03 -0.52 567 110 457 463 898.88 900.08 1018.45 1.20 566 110 456 464 896.26 897.13 1020.50 0.87 566 109 457 465 901.20 901.08 1020.31 -0.12 567 109 458 466 894.21 897.39 1018.68 3.18 563 109 454 467 896.41 896.77 1020.19 0.36 564 110 454 468 899.82 899.51 1020.44 -0.31 565 109 456 469 898.67 899.1 1021.14 0.43 568 110 458 470 898.72 901.36 1021.06 2.64 567 110 457 471 899.62 899.26 1020.99 -0.36 565 110 455 472 898.96 899.56 1020.53 0.60 569 110 459 474 895.02 900.36 1021.07 5.34 569 108 461 475 898.86 898.38 1020.35 -0.48 563 110 453 476 898.16 900.29 1020.31 2.13 567 111 456 477 897.19 898.43 1020.47 1.24 566 110 456 478 897.32 897.96 1020.36 0.64 565 110 455 479 895.06 899.14 1018.55 4.08 566 110 456 480 895.72 898.26 1021.25 2.54 564 110 454 481 898.60 899.31 1021.14 0.71 565 110 455 482 897.77 900.64 1021.10 2.87 564 110 454

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Table J-1: Results of rods measurements (continued). Rod

Number Fissile column length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g)

483 893.42 893.9 1021.05 0.48 561 110 451 484 899.15 899.69 1020.53 0.54 567 109 458 485 894.42 895.53 1020.93 1.11 565 110 455 486 893.09 893.93 1020.29 0.84 564 110 454 487 904.9 895.62 1021.03 -9.28 564 110 454 488 899.78 900.30 1020.52 0.52 566 109 457 489 893.63 894.50 1020.09 0.87 565 111 454 490 897.44 899.26 1020.97 1.82 565 110 455 491 893.29 894.9 1021.12 1.61 564 110 454 492 899.18 898.84 1020.94 -0.34 559 110 449 493 894.83 894.67 1021.01 -0.16 565 110 455 494 896.21 896.92 1021.07 0.71 567 110 457 495 903.76 898.78 1021.03 -4.98 568 109 459 496 892.45 893.02 1020.46 0.57 565 110 455 497 897.75 898.87 1018.58 1.12 567 109 458 498 899.45 899.80 1020.35 0.35 567 110 457 499 895.63 895.98 1020.43 0.35 566 110 456 500 895.05 895.5 1020.88 0.45 564 109 455 501 898.74 899.2 1020.90 0.46 568 110 458 502 895.06 896.1 1020.56 1.04 565 109 456 503 894.98 897.56 1020.38 2.58 566 109 457 504 896.29 897.07 1020.92 0.78 567 110 457 505 893.85 894.47 1020.77 0.62 565 109 456 506 897.69 899.08 1020.97 1.39 566 110 456 507 898.5 899.5 1020.97 1.00 568 109 459 508 892.79 893.47 1020.89 0.68 563 110 453 509 898.96 900.59 1020.84 1.63 565 110 455 510 894.57 894.69 1020.79 0.12 566 110 456 511 898.22 897.21 1021.05 -1.01 565 110 455 512 892.31 892.16 1020.98 -0.15 564 109 455 513 897.53 898.61 1020.84 1.08 566 110 456 514 894.11 895.50 1020.66 1.39 564 110 454 515 899.08 898.50 1021.04 -0.58 567 109 458 516 898.54 898.73 1020.81 0.19 566 109 457 517 898.12 899.62 1020.59 1.50 567 109 458 518 898.75 898.47 1020.68 -0.28 565 109 456 519 898.78 899.24 1020.83 0.46 567 110 457 520 901.48 902.29 1020.38 0.81 569 110 459 521 901.68 902.38 1020.86 0.70 570 110 460 522 897.17 896.92 1020.54 -0.25 565 109 456 523 897.13 896.85 1020.73 -0.28 563 109 454 524 895.04 896.21 1020.76 1.17 566 110 456 525 896.76 898.1 1020.79 1.34 566 109 457 526 900.24 901.30 1021.09 1.06 568 110 458 527 900.18 900.85 1020.34 0.67 568 110 458 528 900.68 900.23 1020.61 -0.45 567 109 458 529 898.69 898.21 1021.01 -0.48 566 110 456 530 912.96 897.66 1020.35 -15.30 566 109 457 531 897.62 900.45 1020.31 2.83 567 111 456 532 895.31 895.91 1020.49 0.60 563 110 453

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Table J-1: Results of rods measurements (continued). Rod

Number Fissile column length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g)

533 894.70 895.20 1021.16 0.50 566 109 457 534 897.08 898.28 1020.45 1.20 567 110 457 535 900.26 901.13 1020.85 0.87 569 110 459 536 897.63 899.30 1020.44 1.67 566 110 456 537 899.24 900.56 1020.80 1.32 567 110 457 538 896.10 896.80 1020.42 0.70 566 109 457 539 894.81 896.24 1020.51 1.43 566 109 457 540 894.33 895.67 1020.38 1.34 565 110 455 541 898.06 899.68 1020.83 1.62 569 110 459 542 900.10 902.23 1020.49 2.13 568 110 458 543 896.16 896.96 1020.53 0.80 565 110 455 544 892.25 893.60 1020.50 1.35 563 110 453 545 896.75 898.05 1021.03 1.30 567 110 457 546 896.51 895.70 1021.09 -0.81 567 110 457 547 894.73 896.49 1021.03 1.76 565 110 455 548 898.70 899.33 1021.02 0.63 568 109 459 549 896.49 899.14 1020.71 2.65 566 110 456 550 895.91 895.92 1020.66 0.01 566 111 455 551 893.16 894.29 1020.82 1.13 564 110 454 552 897.19 898.79 1020.91 1.60 567 110 457 553 899.78 898.91 1020.71 -0.87 568 110 458 554 892.96 892.82 1020.88 -0.14 565 110 455 555 895.54 897.74 1020.78 2.20 566 110 456 556 900.6 896.67 1020.79 -3.93 567 110 457 557 899.30 901.68 1021.15 2.38 567 110 457 558 900.49 900.49 1021.02 0.00 569 110 459 559 894.75 895.70 1020.69 0.95 565 110 455 560 891.54 896.24 1020.98 4.70 563 110 453 561 897.12 893.61 1020.98 -3.51 564 110 454 562 899.09 900.96 1021.04 1.87 568 109 459 563 899.19 899.12 1021.00 -0.07 567 109 458 564 899.54 900.89 1020.65 1.35 566 110 456 565 900.43 899.97 1021.04 -0.46 569 110 459 566 897.03 898.82 1020.98 1.79 565 110 455 567 900.77 899.90 1020.90 -0.87 568 110 458 568 897.42 897.62 1021.00 0.20 565 109 456 569 895.53 897.64 1021.10 2.11 567 110 457 570 897.85 897.51 1020.59 -0.34 570 110 460 571 897.76 899.87 1020.90 2.11 566 109 457 572 892.40 896.65 1020.93 4.25 565 110 455 573 894.56 898.8 1020.71 4.24 566 110 456 574 897.63 900.09 1021.14 2.46 567 110 457 575 898.86 899.40 1020.93 0.54 567 110 457 576 869.48 901.73 1019.28 32.25 567 109 458 577 897.67 899.30 1021.08 1.63 567 110 457 578 892.99 893.18 1020.82 0.19 560 110 450 579 895.44 894.99 1020.68 -0.45 566 110 456 580 896.00 897.13 1020.99 1.13 565 109 456 581 902.05 898.46 1020.82 -3.59 567 109 458 582 899.68 897.5 1020.83 -2.18 560 109 451

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Table J-1: Results of rods measurements (continued). Rod

Number Fissile column length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g)

583 895.33 896.25 1020.69 0.92 562 110 452 584 898.3 898.63 1020.84 0.33 560 111 449 585 897.98 897.53 1020.75 -0.45 571 109 462 586 899.87 900.27 1020.59 0.40 569 111 458 587 896.52 899.98 1020.99 3.46 568 110 458 588 895.62 896.83 1020.90 1.21 564 111 453 589 901.05 899.88 1020.94 -1.17 568 110 458 590 896.33 897.97 1021.00 1.64 563 109 454 591 897.49 898.64 1020.80 1.15 566 110 456 592 900.74 900.59 1020.80 -0.15 566 109 457 593 896.70 896.46 1020.77 -0.24 566 110 456 594 903.2 903.62 1020.84 0.42 568 110 458 595 896.72 896.77 1020.70 0.05 561 109 452 596 898.45 897.85 1021.06 -0.60 562 110 452 597 909.42 902.37 1020.77 -7.05 569 110 459 598 900.05 900.96 1020.99 0.91 570 111 459 599 896.43 895.79 1020.80 -0.64 567 110 457 600 897.79 898.23 1020.76 0.44 565 111 454 601 897.59 897.75 1021.05 0.16 558 110 448 602 899.72 902.68 1020.59 2.96 562 109 453 603 904.49 903.98 1020.70 -0.51 564 110 454 604 898.44 901.1 1021.14 2.66 566 110 456 605 895.60 897.17 1020.96 1.57 567 110 457 606 899.78 897.29 1020.65 -2.49 567 109 458 607 901.19 900.26 1020.65 -0.93 559 110 449 608 898.27 900.00 1021.00 1.73 566 110 456 609 898.04 898.66 1020.58 0.62 568 110 458 610 896.50 895.68 1020.91 -0.82 564 109 455 611 899.59 900.47 1020.81 0.88 565 110 455 612 901.29 898.23 1020.68 -3.06 568 111 457 613 895.57 896.48 1020.53 0.91 566 110 456 614 896.78 898.58 1020.75 1.80 566 110 456 615 896.10 897.59 1020.85 1.49 567 111 456 616 893.07 896.62 1021.00 3.55 560 110 450 617 896.20 900.83 1021.12 4.63 563 109 454 618 898.24 899.35 1020.82 1.11 567 110 457 619 894.22 894.57 1021.10 0.35 564 110 454 620 890.86 895.72 1021.00 4.86 562 109 453 621 894.66 895.57 1021.07 0.91 566 109 457 622 899.57 897.87 1020.62 -1.70 564 110 454 623 899.18 900.03 1020.66 0.85 568 110 458 624 903.26 901.96 1020.74 -1.30 570 111 459 625 898.19 899.44 1020.78 1.25 564 110 454 628 893.11 893.99 1020.80 0.88 565 110 455 630 899.85 900.93 1020.87 1.08 568 110 458 631 900.90 902.08 1020.71 1.18 570 110 460 632 896.03 896.96 1020.15 0.93 566 109 457 633 897.55 900.39 1021.06 2.84 564 110 454 634 899.87 902.72 1020.50 2.85 566 110 456 636 896.69 897.74 1020.90 1.05 566 110 456

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Table J-1: Results of rods measurements (continued). Rod

Number Fissile column length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g)

637 899.79 898.67 1020.92 -1.12 568 111 457 638 898.47 897.77 1020.65 -0.70 562 110 452 639 897.05 897.76 1017.16 0.71 565 109 456 642 898.66 899.90 1017.60 1.24 565 109 456 643 899.28 900.41 1020.59 1.13 568 110 458 644 898.01 898.09 1020.78 0.08 567 110 457 645 901.06 900.52 1020.60 -0.54 567 111 456 646 894.5 895.16 1020.58 0.66 564 110 454 647 894.12 900.92 1020.70 6.80 562 110 452 649 895.8 897.07 1020.95 1.27 565 109 456 651 896.04 895.89 1021.07 -0.15 567 111 456 653 901.24 898.98 1021.11 -2.26 563 110 453 656 892.59 893.62 1020.09 1.03 563 110 453 657 898.86 898.53 1020.24 -0.33 565 109 456 659 897.35 898.31 1020.53 0.96 566 109 457 663 900.06 896.29 1020.80 -3.77 563 110 453 664 898.60 899.23 1020.71 0.63 566 109 457 665 895.63 896.55 1021.29 0.92 567 110 457 666 893.03 895.25 1020.10 2.22 565 110 455 667 894.70 896.66 1021.21 1.96 566 110 456 668 896.02 897.26 1020.97 1.24 567 110 457 669 897.66 899.19 1021.15 1.53 567 110 457 671 893.84 892.35 1021.01 -1.49 566 110 456 672 899.88 902.12 1021.07 2.24 566 110 456 673 896.07 897.96 1021.16 1.89 564 110 454 674 898.24 899.75 1020.79 1.51 568 110 458 675 908.35 899.59 1020.73 -8.76 567 111 456 676 891.02 891.98 1020.51 0.96 565 110 455 677 898.30 899.60 1020.91 1.30 567 110 457 678 894.72 895.34 1020.78 0.62 566 110 456 679 898.73 898.55 1020.47 -0.18 568 109 459 680 896.74 896.85 1020.76 0.11 565 110 455 681 902.30 902.90 1021.07 0.60 571 109 462 682 900.30 899.21 1020.36 -1.09 569 111 458 683 896.71 897.17 1020.91 0.46 566 109 457 684 894.10 893.89 1020.77 -0.21 563 110 453 685 898.66 900.39 1020.98 1.73 566 110 456 686 902.68 904.61 1020.93 1.93 556 110 446 687 898.63 900.08 1020.84 1.45 568 110 458 688 898.20 899.30 1020.68 1.10 565 108 457 689 897.37 898.39 1020.91 1.02 565 109 456 690 896.93 896.48 1020.87 0.45 567 109 458 691 898.06 898.80 1020.68 0.74 566 109 457 692 897.50 898.44 1020.73 0.94 567 110 457 693 896.22 896.04 1020.44 -0.18 564 110 454 694 895.67 895.85 1021.03 0.18 563 110 453 695 898.19 898.81 1020.71 0.62 567 110 457 696 895.91 895.23 1020.58 -0.68 565 109 456 697 896.25 897.74 1020.93 1.49 568 110 458 698 898.78 899.56 1020.38 0.78 565 109 456

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Table J-1: Results of rods measurements (continued). Rod

Number Fissile column length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g)

699 894.46 901.19 1021.17 6.73 567 110 457 700 892.34 894.36 1021.17 2.02 565 110 455 701 900.31 900.93 1021.06 0.62 567 109 458 702 896.86 897.66 1020.62 0.80 566 110 456 703 897.06 897.35 1021.08 0.29 565 110 455 704 901.55 900.87 1020.64 -0.68 567 109 458 705 897.42 898.01 1020.73 0.59 566 110 456 706 897.98 898.66 1020.76 0.68 566 109 457 707 898.04 896.12 1020.54 -1.92 567 109 458 708 895.51 895.08 1021.05 -0.43 563 109 454 709 897.63 898.03 1020.37 0.40 565 110 455 710 896.43 897.10 1020.37 0.67 566 110 456 711 898.02 898.36 1020.39 0.34 566 110 456 712 891.78 892.59 1021.04 0.81 563 110 453 713 896.34 896.38 1021.03 0.04 566 110 456 714 892.64 893.48 1020.44 0.84 562 109 453 715 899.72 901.02 1020.63 1.30 568 109 459 716 896.35 896.99 1020.96 0.64 566 110 456 717 897.26 897.56 1020.59 0.30 566 110 456 718 895.13 895.08 1020.75 -0.05 567 110 457 719 893.96 894.28 1021.07 0.32 563 110 453 720 894.86 896.11 1021.00 1.25 564 110 454 721 894.37 896.50 1020.96 2.13 563 110 453 722 895.66 895.41 1020.83 -0.25 565 109 456 723 899.07 899.60 1020.74 0.53 568 109 459 724 890.51 893.26 1020.59 2.75 562 109 453 725 894.27 894.31 1020.85 0.04 564 109 455 726 894.13 892.36 1020.98 -1.77 562 110 452 727 900.58 899.47 1020.40 -1.11 566 110 456 728 899.17 899.79 1020.81 0.62 567 110 457 729 897.80 897.26 1020.66 -0.54 566 110 456 730 895.43 881.82 1020.81 -13.61 558 110 448 731 899.22 900.22 1021.02 1.00 568 110 458 732 896.52 898.91 1020.75 2.39 567 110 457 733 901.40 899.71 1020.53 -1.69 565 109 456 734 900.47 903.11 1020.86 2.64 568 110 458 735 895.55 896.90 1020.36 1.35 565 110 455 736 893.83 894.23 1020.98 0.40 564 110 454 737 898.53 900.21 1020.98 1.68 565 109 456 738 901.30 902.00 1020.87 0.70 569 110 459 739 898.74 899.01 1020.83 0.27 569 110 459 740 896.39 899.03 1020.99 2.64 567 110 457 741 891.53 892.13 1020.65 0.60 562 110 452 742 897.93 898.48 1021.05 0.55 567 110 457 743 899.59 901.17 1020.40 1.58 563 110 453 744 901.28 899.42 1020.93 -1.86 567 110 457 745 897.70 898.45 1021.04 0.75 568 110 458 746 899.42 899.98 1020.98 0.56 566 110 456 747 895.08 895.38 1020.84 0.30 564 109 455 748 897.55 898.13 1020.65 0.58 566 110 456

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Table J-1: Results of rods measurements (continued). Rod

Number Fissile column length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g)

749 908.95 897.05 1020.97 -11.9 560 109 451 750 895.21 895.81 1020.83 0.60 565 109 456 751 894.70 894.73 1020.89 0.03 564 109 455 752 897.79 899.21 1021.05 1.42 566 109 457 753 894.24 894.04 1020.87 -0.20 566 110 456 754 897.44 898.76 1021.03 1.32 567 109 458 755 895.89 899.25 1020.92 3.36 533 108 425 756 895.63 895.65 1021.02 0.02 565 110 455 757 894.64 895.80 1020.90 1.16 563 109 454 760 896.57 896.99 1020.53 0.42 566 110 456 761 893.36 892.32 1020.96 -1.04 565 110 455 762 895.90 899.56 1020.88 3.66 564 109 455 763 901.49 902.37 1020.83 0.88 568 110 458 764 896.93 897.14 1020.77 0.21 565 111 454 765 894.94 895.24 1020.96 0.30 565 110 455 766 898.75 899.98 1020.69 1.23 566 109 457 767 898.02 900.19 1020.96 2.17 565 109 456 768 891.90 891.81 1020.89 -0.09 564 109 455 769 897.54 898.17 1020.98 0.63 566 110 456 770 900.43 900.76 1020.81 0.33 567 110 457 771 898.40 897.73 1021.00 -0.67 567 110 457 772 901.07 897.99 1020.93 -3.08 567 110 457 773 897.32 898.85 1020.94 1.53 568 110 458 774 901.60 900.16 1021.04 -1.44 568 110 458 775 893.95 895.84 1020.99 1.89 562 109 453 776 899.40 900.55 1020.33 1.15 566 110 456 777 897.52 898.41 1020.87 0.89 567 110 457 778 895.71 897.15 1020.34 1.44 563 109 454 779 899.69 899.09 1021.02 -0.60 564 110 454 780 896.70 897.14 1021.04 0.44 564 109 455 781 895.69 898.16 1020.47 2.47 562 109 453 782 895.44 895.81 1021.04 0.37 565 109 456 783 899.32 902.36 1021.15 3.04 567 109 458 784 893.70 895.12 1020.97 1.42 564 111 453 785 900.18 899.35 1021.04 -0.83 563 110 453 786 899.69 898.87 1020.81 -0.82 562 109 453 788 897.29 899.05 1020.33 1.76 566 110 456 789 898.74 900.30 1020.63 1.56 566 110 456 790 894.71 896.72 1020.63 2.01 565 109 456 791 899.26 900.95 1021.07 1.69 566 111 455 792 896.34 898.26 1020.49 1.92 564 109 455 793 894.95 895.17 1020.34 0.22 565 110 455 794 896.76 896.99 1020.79 0.23 565 110 455 795 901.39 898.85 1020.37 -2.54 569 110 459 796 896.96 898.71 1020.39 1.75 565 109 456 797 899.08 898.47 1020.37 -0.61 567 110 457 798 898.08 899.02 1020.41 0.94 566 110 456 799 900.92 896.42 1020.47 -4.50 563 110 453 800 896.88 898.97 1020.41 2.09 565 109 456 801 897.08 897.00 1020.55 -0.08 567 109 458

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Table J-1: Results of rods measurements (continued). Rod

Number Fissile column length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g)

802 898.17 900.87 1020.89 2.70 566 110 456 803 896.27 897.21 1020.92 0.94 566 109 457 804 896.94 899.17 1020.87 2.23 566 110 456 805 898.26 899.88 1020.76 1.62 566 110 456 806 898.14 899.05 1021.08 0.91 569 110 459 807 898.68 899.14 1020.93 0.46 568 110 458 808 895.34 895.89 1020.73 0.55 566 110 456 809 893.34 894.00 1020.78 0.66 564 109 455 810 894.24 896.20 1020.67 1.96 565 110 455 811 898.38 898.41 1021.01 0.03 568 111 457 812 892.33 892.38 1020.94 0.05 561 109 452 813 901.34 897.71 1021.05 -3.63 567 110 457 814 894.04 895.68 1020.74 1.64 565 109 456 815 896.56 897.90 1020.99 1.34 567 110 457 816 895.96 896.88 1020.90 0.92 568 110 458 817 897.28 898.39 1021.01 1.11 569 110 459 818 897.6 897.61 1020.59 0.01 567 110 457 819 896.06 897.45 1020.96 1.39 566 110 456 820 899.44 900.83 1020.93 1.39 569 109 460 821 901.15 901.31 1021.14 0.16 569 109 460 822 897.30 898.63 1021.10 1.33 567 110 457 823 895.95 897.11 1021.05 1.16 567 110 457 824 892.73 892.78 1020.91 0.05 564 110 454 825 894.4 895.92 1020.98 1.52 566 109 457 826 893.74 894.19 1020.95 0.45 562 109 453 827 894.57 895.83 1020.86 1.26 565 110 455 828 894.52 896.80 1020.43 2.28 565 111 454 829 901.62 901.64 1020.99 0.02 569 109 460 830 893.86 894.66 1020.54 0.80 567 111 456 832 897.18 897.82 1020.91 0.64 568 110 458 833 892.20 898.95 1020.44 6.75 568 110 458 834 903.25 898.68 1020.90 -4.57 566 110 456 835 898.98 899.92 1020.71 0.94 568 110 458 836 894.76 895.13 1020.42 0.37 563 109 454 837 895.57 896.40 1020.65 0.83 566 110 456 838 900.2 900.72 1020.81 0.52 569 110 459 839 890.82 891.94 1020.52 1.12 562 109 453 840 894.53 894.91 1020.53 0.38 565 109 456 841 895.06 895.79 1020.70 0.73 565 110 455 842 896.70 895.99 1020.62 -0.71 566 110 456 843 899.44 899.57 1020.61 0.13 568 109 459 844 895.10 895.69 1020.75 0.59 564 110 454 845 897.60 897.60 1020.89 0.00 565 110 455 846 899.00 899.66 1020.85 0.66 567 110 457 847 894.96 896.17 1020.43 1.21 566 111 455 848 896.79 897.69 1020.70 0.90 565 110 455 849 897.96 898.93 1021.13 0.97 567 110 457 850 904.27 898.80 1020.46 -5.47 565 110 455 851 894.90 898.35 1020.72 3.45 565 110 455 852 898.87 898.76 1020.98 -0.11 566 109 457

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Table J-1: Results of rods measurements (continued). Rod

Number Fissile column length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g)

853 898.56 899.13 1021.07 0.57 567 109 458 854 899.06 901.35 1021.01 2.29 568 110 458 855 898.43 898.68 1021.01 0.25 555 111 444 857 902.60 894.32 1020.61 -8.28 562 109 453 858 894.48 897.79 1021.00 3.31 564 109 455 859 897.66 898.63 1021.02 0.97 565 109 456 860 896.97 896.10 1020.88 -0.87 565 110 455 861 897.76 901.34 1021.06 3.58 567 110 457 862 897.29 898.14 1020.99 0.85 566 109 457 863 900.19 900.47 1020.77 0.28 568 109 459 864 894.50 895.88 1020.94 1.38 565 110 455 865 899.33 899.41 1020.68 0.08 568 110 458 867 895.63 896.49 1020.59 0.86 565 109 456 868 898.16 898.90 1021.00 0.74 567 110 457 869 900.34 900.49 1021.00 0.15 568 109 459 870 898.25 899.54 1020.99 1.29 567 109 458 871 894.42 894.75 1020.71 0.33 566 111 455 872 899.18 901.56 1021.23 2.38 568 110 458 873 894.64 896.09 1020.78 1.45 564 110 454 874 897.98 898.84 1021.05 0.86 566 109 457 875 895.63 897.47 1020.80 1.84 574 111 463 876 896.52 898.75 1020.47 2.23 564 110 454 877 895.68 896.34 1020.99 0.66 567 111 456 878 890.94 891.61 1020.73 0.67 561 110 451 879 898.36 898.06 1021.04 -0.30 567 110 457 880 896.70 894.02 1020.74 -2.68 567 111 456 881 899.16 899.86 1021.03 0.70 567 110 457 882 897.88 898.42 1021.00 0.54 567 109 458 883 896.82 899.54 1020.99 2.72 564 110 454 884 897.43 897.97 1021.05 0.54 564 110 454 887 894.79 895.11 1021.04 0.32 564 110 454 888 896.12 896.50 1021.08 0.38 564 109 455 889 899.78 896.60 1021.02 -3.18 566 109 457 890 896.93 898.89 1020.67 1.96 564 110 454 891 896.34 897.03 1021.07 0.69 568 109 459 892 894.94 893.03 1020.76 -1.91 564 110 454 893 892.04 893.17 1020.66 1.13 563 110 453 894 898.67 900.07 1020.72 1.40 566 110 456 895 897.98 897.79 1020.63 -0.19 110 896 891.12 893.02 1020.66 1.90 561 110 451 897 898.15 897.54 1021.07 -0.61 566 110 456 898 894.67 894.21 1020.97 -0.46 566 110 456 899 896.21 897.12 1021.00 0.91 567 110 457 900 895.09 895.66 1020.93 0.57 565 110 455 901 897.55 898.56 1020.77 1.01 568 110 458 902 896.07 898.44 1020.69 2.37 565 110 455 903 899.09 900.13 1021.04 1.04 567 110 457 904 896.60 897.12 1021.13 0.52 566 110 456 905 898.92 899.85 1020.99 0.93 569 110 459 906 895.42 895.45 1021.10 0.03 565 110 455

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Table J-1: Results of rods measurements (continued). Rod

Number Fissile column length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g)

907 895.26 895.64 1021.02 0.38 562 110 452 908 892.98 893.57 1021.21 0.59 565 110 455 909 895.68 896.15 1020.80 0.47 567 111 456 910 895.92 896.03 1020.71 0.11 565 110 455 911 894.72 895.23 1020.74 0.51 563 110 453 912 899.66 899.81 1020.57 0.15 567 110 457 913 900.14 901.37 1020.87 1.23 569 110 459 914 895.93 896.24 1020.68 0.31 566 110 456 915 900.08 900.35 1021.05 0.27 569 110 459 916 899.14 900.75 1021.03 1.61 567 110 457 917 898.13 898.60 1020.80 0.47 567 110 457 918 895.57 896.44 1020.81 0.87 567 111 456 919 897.74 897.24 1021.06 -0.50 565 110 455 920 893.06 894.01 1020.53 0.95 565 110 455 921 892.96 893.39 1020.69 0.43 564 109 455 922 900.25 901.09 1020.49 0.84 567 109 458 923 898.42 899.42 1020.76 1.00 569 110 459 924 895.50 896.10 1021.03 0.60 566 111 455 925 899.65 898.24 1021.08 -1.41 565 109 456 926 897.43 898.71 1021.25 1.28 567 110 457 927 896.10 896.80 1020.81 0.70 566 110 456 928 892.21 893.49 1021.00 1.28 563 109 454 929 896.34 897.2 1021.04 0.86 568 110 458 930 898.38 899.31 1020.95 0.93 566 109 457 931 896.64 897.28 1021.20 0.64 567 110 457 932 894.84 896.10 1020.92 1.26 565 110 455 933 892.86 894.14 1021.06 1.28 564 109 455 934 898.54 899.25 1021.19 0.71 568 110 458 935 896.8 897.5 1021.13 0.70 567 109 458 936 897.52 897.81 1020.50 0.29 566 109 457 937 898.06 898.36 1021.10 0.30 567 110 457 938 896.76 897.63 1020.72 0.87 566 109 457 939 897.66 897.82 1020.30 0.16 562 110 452 940 899.44 900.13 1021.13 0.69 568 110 458 941 897.75 898.21 1021.21 0.46 567 109 458 942 898.18 898.27 1020.99 0.09 566 109 457 943 895.88 896.5 1021.13 0.62 565 110 455 944 899.16 899.97 1021.24 0.81 568 111 457 945 902.3 902.74 1020.96 0.44 568 110 458 946 895.4 895.97 1021.01 0.57 566 110 456 947 896.14 897.24 1020.78 1.10 567 110 457 948 897.52 898.64 1021.06 1.12 566 109 457 949 900.02 900.12 1020.85 0.10 566 109 457 950 897.45 898.94 1021.22 1.49 567 110 457 951 898.87 899.79 1020.59 0.92 569 110 459 952 894.11 894.51 1020.50 0.4 564 110 454 953 895.72 896.64 1021.03 0.92 567 109 458 954 896.18 899.21 1020.35 3.03 566 109 457 955 899.01 900.59 1020.99 1.58 569 109 460 956 892.04 894.56 1020.63 2.52 562 110 452

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Table J-1: Results of rods measurements (continued). Rod

Number Fissile column length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g)

957 894.89 896.08 1020.63 1.19 563 109 454 958 899.75 897.99 1020.79 -1.76 566 110 456 960 896.37 897.75 1020.69 1.38 567 110 457 961 898.47 900.61 1020.63 2.14 565 111 454 962 904.24 905.22 1020.79 0.98 569 109 460 963 898.02 898.50 1020.63 0.48 567 110 457 964 896.53 898.03 1021.10 1.50 567 111 456 965 889.05 890.76 1020.75 1.71 562 109 453 966 898.14 899.45 1021.04 1.31 568 111 457 967 896.46 897.48 1020.89 1.02 565 110 455 968 889.82 891.80 1021.25 1.98 562 110 452 969 902.20 900.16 1020.99 -2.04 568 109 459 970 897.54 896.37 1020.88 -1.17 566 109 457 971 901.60 901.89 1021.01 0.29 567 109 458 972 897.37 898.88 1020.93 1.51 567 110 457 973 898.91 899.66 1020.62 0.75 568 109 459 974 898.93 900.14 1020.87 1.21 567 109 458 975 898.24 898.47 1020.85 0.23 566 110 456 976 899.31 900.38 1020.73 1.07 568 110 458 977 893.61 894.93 1020.77 1.32 565 110 455 978 898.01 898.8 1020.91 0.79 566 109 457 979 898.26 899.18 1020.37 0.92 568 111 457 980 896.64 898.05 1020.54 1.41 565 110 455 981 902.49 885.79 1020.91 -16.70 560 109 451 983 895.88 897.01 1020.69 1.13 565 109 456 984 894.23 895.28 1020.66 1.05 563 111 452 985 899.46 900.87 1018.86 1.41 568 110 458 986 893.85 896.30 1020.95 2.45 566 110 456 987 895.74 897.15 1020.72 1.41 565 109 456 988 900.89 902.47 1020.93 1.58 570 110 460 989 899.06 900.48 1021.27 1.42 568 110 458 990 897.62 897.27 1020.86 -0.35 566 110 456 991 900.44 899.72 1020.80 -0.72 568 111 457 992 890.85 892.72 1021.22 1.87 564 109 455 993 896.69 895.20 1021.24 -1.49 566 109 457 994 898.83 899.70 1020.97 0.87 566 110 456 995 898.18 898.04 1021.12 -0.14 567 110 457 996 898.30 894.94 1021.04 -3.36 564 110 454 997 895.76 896.32 1021.08 0.56 564 110 454 998 897.55 898.81 1021.12 1.26 568 110 458 999 901.54 901.52 1021.12 -0.02 568 110 458 1000 901.05 900.06 1021.12 -0.99 567 110 457 1001 895.25 896.71 1020.90 1.29 565 109 456 1002 892.18 893.24 1020.93 1.06 564 109 455 1003 896.66 898.06 1021.13 1.40 564 110 454 1005 898.06 899.10 1020.80 1.29 568 110 458 1006 891.03 893.07 1020.86 1.29 563 109 454 1007 894.78 895.56 1021.11 1.29 564 110 454 1008 894.65 891.56 1020.77 1.29 563 109 454 1009 896.90 898.62 1020.86 1.72 566 110 456

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Table J-1: Results of rods measurements (continued). Rod

Number Fissile column length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g)

1010 896.07 896.46 1021.03 0.39 109 1011 896.07 897.63 1021.06 1.56 565 110 455 1012 895.82 896.34 1020.94 0.52 566 110 456 1013 897.15 898.36 1020.86 1.21 567 110 457 1014 897.18 895.60 1020.85 -1.58 565 110 455 1015 891.63 892.64 1020.84 1.01 560 108 452 1016 897.25 898.46 1020.86 1.21 564 110 454 1017 889.94 893.94 1021.07 4.00 559 109 450 1018 896.53 897.43 1021.00 0.90 566 109 457 1019 899.75 900.60 1021.09 0.85 562 110 452 1020 895.83 896.22 1020.78 1.29 562 109 453 1021 894.76 896.24 1021.03 1.48 565 110 455 1022 902.16 902.89 1021.09 0.73 566 110 456 1023 891.21 892.74 1021.02 1.53 562 110 452 1024 899.27 898.95 1021.01 -0.32 567 110 457 1025 900.07 900.52 1020.89 0.45 568 110 458 1026 897.79 899.00 1021.00 1.21 567 110 457 1027 897.81 899.08 1021.00 1.27 567 110 457 1028 895.89 901.32 1021.04 5.43 563 111 452 1029 891.80 894.25 1021.15 2.45 560 110 450 1030 893.88 895.14 1021.03 1.26 564 110 454 1031 899.71 899.26 1021.01 -0.45 567 110 457 1032 897.96 901.98 1020.99 4.02 568 109 459 1033 897.04 898.18 1020.86 1.14 565 109 456 1034 899.60 899.09 1021.04 -0.51 567 110 457 1035 899.07 899.12 1021.05 0.05 566 109 457 1037 898.80 902.23 1020.37 3.43 562 111 451 1038 900.53 899.27 1020.98 -1.26 565 110 455 1039 895.65 896.40 1020.53 0.75 565 110 455 1040 894.22 894.67 1020.99 0.45 565 111 454 1041 896.78 899.16 1020.91 2.38 564 109 455 1042 899.63 896.25 1021.17 -3.38 568 110 458 1043 892.21 893.42 1021.07 1.21 560 110 450 1044 897.99 898.79 1020.80 0.80 566 110 456 1045 895.26 894.31 1020.94 -0.95 562 110 452 1046 896.39 898.39 1021.03 2.00 564 111 453 1047 898.45 898.50 1020.81 0.05 566 110 456 1048 894.84 896.04 1021.02 1.20 565 110 455 1049 895.61 896.90 1021.14 1.29 565 110 455 1050 894.48 896.55 1020.84 2.07 560 110 450 1051 901.14 899.10 1021.03 -2.04 568 110 458 1052 896.45 896.99 1021.15 0.54 561 110 451 1053 900.33 899.40 1020.96 -0.93 566 109 457 1054 896.24 896.36 1021.19 0.12 563 109 454 1055 898.72 899.25 1021.15 0.53 567 109 458 1056 898.04 897.78 1020.92 -0.26 568 109 459 1057 899.08 898.70 1021.18 -0.38 568 110 458 1058 899.09 898.46 1020.75 -0.63 566 110 456 1059 894.20 894.40 1020.89 0.20 565 110 455 1060 897.70 899.02 1021.00 1.32 567 110 457

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Table J-1: Results of rods measurements (continued). Rod

Number Fissile column length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g) 1061 900.73 900.85 1020.85 0.12 567 109 458 1062 895.88 901.26 1020.74 5.38 567 110 457 1063 898.46 899.07 1021.18 0.61 562 110 452 1064 898.71 900.22 1020.66 1.51 568 109 459 1065 897.47 899.13 1021.01 1.66 566 109 457 1066 899.24 900.52 1021.12 1.28 566 110 456 1067 896.71 898.63 1021.05 1.92 566 110 456 1068 894.67 894.71 1021.12 0.04 565 110 455 1069 898.44 898.64 1021.11 0.20 565 109 456 1070 894.22 895.72 1021.01 1.50 563 110 453 1071 899.37 898.16 1020.98 -1.21 566 109 457 1072 905.98 901.57 1020.88 -4.41 566 111 455 1073 893.25 894.12 1020.96 0.87 565 110 455 1074 897.48 898.29 1020.95 0.81 567 110 457 1075 898.74 898.91 1021.20 0.17 567 110 457 1076 899.30 898.85 1020.93 -0.45 567 110 457 1077 893.10 893.92 1021.02 0.82 565 111 454 1078 897.39 897.24 1021.06 -0.15 565 109 456 1079 895.96 897.84 1021.04 1.88 564 110 454 1080 893.18 892.07 1021.08 -1.11 564 109 455 1081 894.00 893.93 1021.07 -0.07 565 109 456 1082 896.52 896.80 1020.91 0.28 568 110 458 1083 895.89 896.92 1021.17 1.03 567 111 456 1084 895.14 894.93 1021.16 -0.21 563 110 453 1085 897.27 897.99 1021.24 0.72 568 110 458 1086 894.97 894.85 1020.85 -0.12 565 109 456 1087 897.73 898.49 1020.91 0.76 566 109 457 1088 899.64 900.68 1020.90 1.04 567 110 457 1089 899.26 898.28 1020.89 -0.98 566 110 456 1090 896.39 897.32 1021.04 0.93 567 111 456 1091 894.64 894.88 1021.07 0.24 563 109 454 1092 897.90 898.92 1021.10 1.02 565 110 455 1093 895.10 894.46 1021.16 -0.64 566 110 456 1094 896.44 898.07 1021.04 1.63 565 109 456 1095 895.82 896.03 1020.21 0.21 564 109 455 1096 898.12 900.46 1020.95 2.34 567 109 458 1097 900.03 899.94 1021.09 -0.09 568 109 459 1098 894.06 894.16 1020.83 0.10 566 110 456 1099 898.48 899.83 1020.81 1.35 568 110 458 1100 897.63 898.21 1020.71 0.58 567 110 457 1101 899.09 899.10 1020.96 0.01 569 110 459 1102 897.60 898.61 1021.06 1.01 567 109 458 1103 897.38 896.83 1021.40 -0.55 566 109 457 1104 894.96 896.07 1021.13 1.11 566 110 456 1105 895.58 897.16 1020.59 1.58 564 110 454 1106 899.65 900.27 1021.14 0.62 569 110 459 1107 895.65 895.79 1020.91 0.14 564 109 455 1108 898.55 899.05 1020.86 0.50 566 110 456 1109 900.17 900.38 1021.11 0.21 568 110 458 1111 896.05 895.48 1021.13 -0.57 567 111 456

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Table J-1: Results of rods measurements (continued). Rod

Number Fissile column length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g)

1112 897.27 897.81 1021.15 0.54 568 110 458 1113 894.20 895.56 1021.02 1.36 566 110 456 1114 893.89 894.35 1021.05 0.46 563 110 453 1115 897.88 898.80 1020.80 0.92 569 110 459 1116 897.35 895.40 1020.94 -1.95 567 110 457 1117 896.25 896.16 1021.02 -0.09 563 109 454 1118 897.97 898.96 1021.03 0.99 567 109 458 1119 896.05 893.19 1021.07 -2.86 565 109 456 1121 897.48 897.61 1020.95 0.13 568 110 458 1122 897.32 898.07 1020.92 0.75 567 110 457 1123 899.82 900.08 1020.95 0.26 570 111 459 1124 896.48 896.87 1020.73 0.39 564 109 455 1125 898.26 896.79 1021.16 -1.47 566 111 455 1126 897.09 897.35 1021.17 0.26 568 110 458 1127 896.89 897.88 1020.84 0.99 565 110 455 1128 897.09 898.61 1021.00 1.52 566 109 457 1129 895.90 896.51 1021.00 0.61 566 110 456 1130 897.38 896.97 1021.13 -0.41 565 109 456 1131 897.77 897.87 1020.97 0.10 565 111 454 1132 894.63 893.65 1021.01 -0.98 565 110 455 1133 898.91 898.99 1020.69 0.08 566 110 456 1135 898.15 896.26 1020.96 -1.89 567 110 457 1136 897.15 896.63 1021.16 -0.52 567 109 458 1137 893.95 893.58 1021.03 -0.37 563 109 454 1138 898.39 898.39 1020.98 0.00 566 110 456 1139 894.89 895.44 1021.13 0.55 563 109 454 1140 894.52 896.71 1020.78 2.19 565 110 455 1141 900.74 900.97 1021.19 0.23 567 110 457 1142 895.44 897.73 1020.93 2.29 564 109 455 1143 893.96 893.89 1021.01 -0.07 563 109 454 1144 892.38 893.09 1020.82 0.71 560 109 451 1145 897.33 896.14 1020.86 -1.19 566 110 456 1146 896.76 896.79 1020.89 0.03 566 110 456 1147 897.52 896.07 1020.85 -1.45 564 109 455 1148 896.94 898.14 1021.08 1.20 566 109 457 1149 899.25 898.99 1021.16 -0.26 569 110 459 1150 896.43 897.38 1020.98 0.95 568 110 458 1152 898.48 898.93 1020.62 0.45 570 110 460 1153 895.93 897.05 1020.97 1.12 565 110 455 1154 898.11 899.41 1021.17 1.30 567 110 457 1155 896.00 895.70 1020.98 -0.30 565 110 455 1157 896.93 898.33 1021.02 1.40 565 110 455 1158 896.76 897.13 1021.15 0.37 567 110 457 1159 898.56 898.27 1021.01 -0.29 568 110 458 1160 898.53 899.97 1021.04 1.44 567 110 457 1161 896.90 897.98 1021.14 1.08 568 109 459 1162 898.70 899.82 1021.03 1.29 568 110 458 1163 897.00 897.38 1021.05 0.38 568 110 458 1165 898.22 898.73 1020.77 0.51 568 110 458 1166 897.96 899.11 1020.87 1.15 567 110 457

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Table J-1: Results of rods measurements (continued). Rod Number Fissile column

length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g)

1168 903.20 905.04 1021.12 1.84 571 110 461 1169 894.76 895.13 1021.20 0.37 565 110 455 1170 897.12 898.42 1020.69 1.29 569 110 459 1171 897.88 899.21 1020.88 1.33 570 110 460 1172 898.77 897.68 1020.80 -1.09 564 109 455 1173 896.96 897.63 1020.97 0.67 567 110 457 1176 897.08 897.39 1021.26 0.31 566 109 457 1177 893.42 892.93 1021.20 -0.49 566 110 456 1178 898.83 899.14 1021.18 0.31 567 110 457 1179 896.12 896.54 1020.86 0.42 566 110 456 1180 893.81 894.51 1021.09 0.70 566 109 457 1181 896.47 897.55 1021.00 1.08 566 109 457 1182 898.03 899.85 1020.99 1.82 567 110 457 1184 899.77 899.87 1021.08 0.10 566 109 457 1185 903.93 897.93 1021.22 -6.00 564 110 454 1186 896.83 896.74 1021.01 -0.09 567 109 458 1187 897.86 897.96 1020.89 0.10 568 109 459 1188 897.16 899.06 1020.73 1.90 566 109 457 1190 897.59 898.24 1021.10 0.65 567 109 458 1191 895.06 901.18 1021.17 6.12 564 110 454 1192 898.55 899.77 1021.01 1.22 568 110 458 1193 895.74 896.62 1020.37 0.88 566 109 457 1194 896.84 897.23 1021.09 0.39 567 109 458 1195 894.06 900.17 1020.94 6.11 564 108 456 1196 894.76 894.62 1021.14 -0.14 566 110 456 1197 895.30 897.28 1021.03 1.98 563 108 455 1198 893.74 894.11 1020.81 0.37 562 109 453 1199 897.54 894.05 1021.13 -3.49 565 109 456 1200 895.80 895.01 1021.00 -0.79 565 110 455 1201 896.17 896.54 1021.02 0.37 566 109 457 1202 899.60 899.80 1020.88 0.20 569 109 460 1203 899.06 899.69 1021.24 0.63 569 110 459 1204 898.44 898.79 1020.78 0.35 568 109 459 1205 897.71 898.07 1020.98 0.36 567 110 457 1206 898.47 900.30 1020.64 1.83 566 109 457 1207 897.06 898.18 1020.73 1.12 565 110 455 1208 895.12 895.45 1021.04 0.33 563 109 454 1209 898.06 900.03 1021.06 1.97 567 109 458 1210 895.05 895.95 1021.00 0.90 563 108 455 1211 895.63 898.72 1020.53 3.09 567 110 457 1212 897.43 898.26 1020.89 0.83 568 109 459 1213 898.02 899.70 1020.91 1.68 567 109 458 1214 898.67 901.09 1020.98 2.42 568 109 459 1215 898.00 899.83 1020.88 1.83 564 109 455 1216 895.16 896.91 1020.84 1.75 562 109 453 1217 894.09 894.49 1020.65 0.40 565 110 455 1218 898.93 899.45 1020.98 0.52 568 110 458 1219 897.51 899.13 1020.73 1.62 566 109 457 1220 893.62 894.84 1020.97 1.22 566 109 457 1221 896.76 897.53 1020.70 0.77 565 110 455

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Table J-1: Results of rods measurements (continued). Rod Number Fissile column

length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g)

1222 901.06 897.05 1020.62 -4.01 561 109 452 1223 899.10 900.77 1021.15 1.67 568 110 458 1224 895.90 896.47 1020.94 0.57 566 109 457 1225 896.05 896.84 1020.96 0.79 566 109 457 1226 896.01 898.33 1020.87 2.32 564 110 454 1227 901.90 902.38 1021.04 0.48 568 110 458 1229 895.03 897.98 1020.80 2.95 568 110 458 1230 897.84 898.39 1020.85 0.55 567 110 457 1231 893.61 895.74 1020.78 2.13 565 109 456 1232 898.10 898.76 1021.23 0.66 569 110 459 1233 899.96 902.49 1020.80 2.53 567 110 457 1234 893.90 895.12 1021.02 1.22 565 108 457 1235 900.52 901.41 1021.13 0.89 566 109 457 1236 891.82 892.05 1020.86 0.23 561 108 453 1237 898.15 894.98 1021.26 -3.17 566 110 456 1238 899.25 900.04 1020.90 0.79 568 110 458 1239 899.57 899.50 1020.93 -0.07 567 110 457 1240 893.03 896.35 1021.24 3.32 563 110 453 1241 893.88 894.78 1020.90 0.90 565 110 455 1242 894.86 896.95 1020.25 2.09 565 110 455 1243 894.62 894.77 1020.91 0.15 566 110 456 1244 897.98 898.87 1021.19 0.89 567 110 457 1245 899.71 898.33 1021.23 -1.38 568 110 458 1246 897.32 898.73 1021.06 1.41 566 109 457 1247 902.36 901.51 1020.92 -0.85 568 110 458 1248 893.70 894.62 1020.93 0.92 565 109 456 1249 895.18 897.11 1020.78 1.93 556 110 446 1250 893.78 893.73 1020.99 -0.05 565 110 455 1251 898.55 898.94 1020.57 0.39 566 110 456 1252 895.12 896.33 1020.50 1.21 563 110 453 1253 893.35 895.41 1020.19 2.06 564 110 454 1254 898.36 898.21 1020.97 -0.15 566 110 456 1255 893.47 894.83 1020.84 1.36 565 110 455 1256 897.16 898.13 1020.93 0.97 567 110 457 1257 894.72 896.49 1020.90 1.77 565 110 455 1258 898.06 899.1 1021.25 1.04 566 109 457 1259 898.46 889.5 1020.96 -8.96 568 109 459 1260 894.67 896.06 1020.42 1.39 562 110 452 1261 902.91 903.36 1020.98 0.45 571 110 461 1262 902.44 897.87 1021.02 -4.57 565 109 456 1263 895.85 897.53 1020.51 1.68 566 110 456 1264 894.15 894.80 1020.96 0.65 564 110 454 1265 898.85 899.05 1020.59 0.20 566 110 456 1266 895.25 896.9 1020.95 1.65 564 110 454 1267 896.42 898.06 1021.12 1.64 568 110 458 1268 894.06 895.98 1021.15 1.92 568 110 458 1269 898.01 898.28 1021.16 0.27 566 109 457 1270 897.76 899.63 1020.64 1.87 566 110 456 1271 899.18 897.72 1021.05 -1.46 567 110 457 1272 903.56 903.41 1020.44 -0.15 570 109 461

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Table J-1: Results of rods measurements (continued). Rod

Number Fissile column length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g)

1273 894.82 897.68 1020.56 2.86 563 110 453 1274 896.38 896.76 1020.32 0.38 566 110 456 1275 896.22 896.32 1020.94 0.10 566 110 456 1285 899.84 901.73 1020.80 1.89 566 110 456 1287 899.10 900.92 1020.67 1.82 567 110 457 1289 895.73 895.98 1020.96 0.25 565 109 456 1299 898.02 899.04 1020.73 1.02 567 110 457 1326 893.79 893.07 1021.10 -0.72 561 109 452 1327 900.73 899.55 1021.00 -1.18 566 110 456 1328 890.50 891.96 1021.17 1.46 562 109 453 1329 894.79 895.05 1021.01 0.26 564 109 455 1330 893.76 894.51 1021.06 0.75 566 110 456 1331 893.30 894.00 1020.89 0.70 565 110 455 1332 896.96 897.43 1020.55 0.47 565 109 456 1333 897.54 898.66 1021.06 1.12 566 110 456 1334 892.02 891.27 1020.85 -0.75 562 109 453 1335 898.22 881.75 1021.10 -16.47 558 110 448 1336 900.50 898.00 1021.03 -2.50 566 110 456 1338 904.95 902.17 1020.95 -2.78 565 109 456 1339 895.43 895.70 1020.63 0.27 563 110 453 1340 898.52 900.71 1020.80 2.19 567 110 457 1341 904.60 901.81 1021.01 -2.79 569 110 459 1342 897.70 899.44 1020.84 1.74 565 110 455 1343 892.30 891.59 1020.85 -0.71 562 110 452 1344 898.73 899.19 1020.54 0.46 566 110 456 1345 899.51 900.60 1020.95 1.09 567 109 458 1346 898.17 899.50 1021.07 1.33 566 110 456 1347 896.77 900.87 1021.25 4.10 564 110 454 1348 901.19 901.61 1021.22 0.42 567 109 458 1349 899.62 899.62 1020.88 0.00 568 110 458 1351 898.88 898.98 1020.73 0.10 566 109 457 1352 896.76 897.63 1021.10 0.87 566 109 457 1353 899.46 900.82 1021.06 1.36 570 110 460 1354 895.30 896.70 1021.00 1.40 567 109 458 1355 899.25 900.49 1020.88 1.24 567 110 457 1356 896.08 896.81 1020.97 0.73 564 109 455 1357 896.52 898.21 1021.12 1.69 566 109 457 1358 895.56 896.26 1020.73 0.70 565 109 456 1359 895.44 896.12 1021.00 0.68 563 109 454

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Table J-1: Results of rods measurements (continued).

Rods of Category 1 after repairing

Rod Number

Fissile column length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g)

473 894.09 896.97 1017.79 2.88 562 110 452 459 897.71 902.94 1017.62 5.23 565 109 456 856 896.23 897.40 1017.87 1.17 567 110 457 959 848.73 901.64 1013.98 52.91 541 110 431 1004 890.38 892.86 1017.83 2.48 110

Rods of Category 2

Rod

Number Fissile column length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g)

1301 class B pellets 897.7 1020.98 551 110 441 1304 class B pellets 896.45 1020.97 557 110 447 1305 class B pellets 896.33 1020.68 552 110 442 1307 class B pellets 896.8 1020.69 548 110 438 1308 class B pellets 899.88 1020.68 552 110 442 1309 class B pellets 898.46 1020.86 554 110 444 1311 class B pellets 897.41 1020.98 554 110 444 1312 class B pellets 897.5 1021.18 554 110 444 1313 class B pellets 897.44 1021.06 548 109 439 1315 class B pellets 896.93 1020.98 566 110 456 1317 class B pellets 898.26 1020.79 547 110 437 1319 class B pellets 897.27 1020.99 558 110 448 1320 class B pellets 896.4 1020.92 561 110 451 1321 class B pellets 896.64 1020.97 551 110 441 1322 class B pellets 896.6 1020.74 561 110 451 1324 class B pellets 896.94 1020.71 551 109 442 1325 class B pellets 896.86 1020.74 560 111 449 1337 class B pellets 898.74 1020.67 563 110 453 1350 class B pellets 896.93 1020.85 558 110 448

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Table J-1: Results of rods measurements (continued). Results for 1261 rods

Rod

Number Fissile column length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g)

Minimum 848.73 881.75 1013.98 -16.7 533 108 425 Mean 897.02 897.65 1020.82 0.64 565.53 109.74 455.78

Maximum 912.96 905.22 1021.70 52.91 574 111 463 Standard deviation

3.06 2.54 0.4 2.51 2.85 0.6 2.82

Total 709738 138278 572009

Results for 1242 rods of Category 1

Rod Number

Fissile column length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g)

Maximum 912.96 905.22 1021.70 52.91 574 111 463 Mean 897.02 897.66 1020.82 0.64 565.69 109.7 455.95

Minimum 848.73 881.75 1013.98 -16.70 533 108 425 Standard deviation

3.06 2.56 0.41 2.51 2.47 0.61 2.43

Total 699192 136189 563552

Results for 1237 non-repaired rods of Category 1

Rod Number

Fissile column length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g)

Maximum 912.96 905.22 1021.70 32.25 574 111 463 Mean 897.07 897.65 1020.84 0.59 565.71 109.74 455.97

Minimum 869.48 881.75 1017.16 -16.7 533 108 425 Standard deviation

2.74 2.55 0.31 2.02 2.37 0.61 2.33

Total 696957 135640 561756

Results for 5 repaired rods of Category 1

Rod Number

Fissile column length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g)

Maximum 897.71 902.94 1017.87 52.91 567 110 457.00 Mean 885.43 898.36 1017.02 12.93 558.75 109.80 449.00

Minimum 848.73 892.86 1013.98 -16.70 541 109 431.00 Standard deviation

20.70 4.03 1.7 22.4 12.01 0.45 12.19

Total 2235 546 1796

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Table J-1: Results of rods measurements (continued).

Results for 19 rods of Category 2

Rod Number

Fissile column length before recladding

Fissile column length after recladding

Fuel rod length

Lc2-Lc1 Weight TSBI + Uranium

Weight TSBI Weight of Uranium

Lc1 (mm) Lc2 (mm) Lcc (mm) ∆∆∆∆L (mm) Pc (g) Pbi(g) ∆∆∆∆P=Pc-Pbi (g)

Maximum 899.88 1021.18 566 111 456 Mean 897.34 1020.87 555.1 109.95 445.11

Minimum 896.33 1020.67 547 109 437 Standard deviation

0.93 0.15 5.45 0.4 5.3

Total 10546 2089 8457

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Measurements of claddings

Three hundred measurements of UO2 rods’ cladding outer diameter were made with Palmer device. The measurements were performed on three different heights, indicated as A, B, and C in Figure below. Calibration range comprised between 0 mm and 25 mm, the precision of the measurement is ±0,005 mm. The results of the measurements performed at points A, B, and C are indicated in Table J-2 in columns designated as HA, HB, and HC, accordingly.

A

B

C

150

510

UO2 Rod

Cotes en mm

250

Figure J-1. Caption

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Table J-2: Rods’ cladding diameter measurements.

Rod Number HC (mm) HB (mm) HA (mm) Temperature (°C) 0580 9.483 9.485 9.488 20°14 1203 9.492 9.489 9.494 1345 9.493 9.496 9.495 0777 9.494 9.494 9.495 19°98 0735 9.494 9.494 9.492 0470 9.489 9.490 9.485 0346 9.486 9.491 9.492 0324 9.494 9.497 9.495 0539 9.486 9.491 9.490 0257 9.485 9.492 9.493 0203 9.494 9.495 9.493 0011 9.496 9.495 9.496 1086 9.492 9.489 9.493 0873 9.495 9.495 9.491 0631 9.496 9.493 9.497 0796 9.484 9.492 9.492 0254 9.490 9.490 9.494 0130 9.484 9.488 9.486 20°01 0642 9.491 9.492 9.495 1058 9.490 9.487 9.491 1336 9.492 9.491 9.493 0241 9.497 9.496 9.497 1235 9.492 9.489 9.488 0800 9.486 9.486 9.485 1331 9.490 9.493 9.493 0354 9.494 9.495 9.488 0729 9.490 9.492 9.491 0098 9.496 9.494 9.498 0194 9.498 9.497 9.497 0273 9.489 9.488 9.492 0456 9.495 9.494 9.497 0751 9.480 9.481 9.485 20°06 0732 9.495 9.491 9.495 1218 9.490 9.492 9.492 0502 9.494 9.495 9.490 1076 9.492 9.489 9.491 0510 9.495 9.496 9.497 0609 9.491 9.495 9.494 1055 9.485 9.485 9.487 0954 9.490 9.494 9.496 0676 9.492 9.490 9.492 0516 9.482 9.485 9.486 1326 9.490 9.492 9.492 0830 9.498 9.498 9.497 1130 9.490 9.490 9.489

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0922 9.492 9.490 9.489 0747 9.490 9.491 9.493 0137 9.490 9.493 9.492 0679 9.492 9.493 9.492

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Table J-2: Rods’ cladding diameter measurements (continued).

Rod Number HC (mm) HB (mm) HA (mm) Temperature (°C) 0268 9.497 9.495 9.498 1135 9.495 9.491 9.497 1046 9.495 9.495 9.495 1170 9.491 9.491 9.489 1239 9.494 9.496 9.499 0554 9.495 9.499 9.494 20°10 0094 9.498 9.498 9.499 0839 9.486 9.486 9.483 0681 9.489 9.492 9.489 0903 9.494 9.493 9.492 1177 9.492 9.492 9.496 20°13 0695 9.496 9.497 9.495 0579 9.499 9.500 9.500 1184 9.488 9.489 9.489 1359 9.490 9.489 9.493 20°16 0736 9.489 9.491 9.493 0126 9.481 9.482 9.482 1017 9.487 9.483 9.494 0986 9.492 9.492 9.497 20°13 0919 9.495 9.495 9.494 0625 9.494 9.492 9.494 0823 9.498 9.497 9.498 0457 9.482 9.479 9.481 0773 9.488 9.492 9.491 0330 9.495 9.494 9.492 0748 9.498 9.495 9.497 0858 9.486 9.488 9.485 0610 9.497 9.500 9.498 0498 9.498 9.491 9.496 1173 9.494 9.496 9.493 0550 9.499 9.498 9.501 0933 9.492 9.495 9.494 0772 9.498 9.498 9.496 0052 9.495 9.495 9.498 0783 9.488 9.488 9.489 0708 9.484 9.483 9.486 0678 9.493 9.493 9.491 0692 9.493 9.496 9.495 0709 9.489 9.492 9.488 1232 9.498 9.495 9.496 0636 9.495 9.495 9.495 0102 9.494 9.494 9.496 0015 9.491 9.495 9.491 1226 9.498 9.497 9.497 0586 9.501 9.499 9.496

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0027 9.500 9.495 9.498 1125 9.496 9.500 9.499 0552 9.498 9.498 9.495 1020 9.490 9.495 9.499 0140 9.493 9.495 9.497 0023 9.488 9.485 9.488

HC HB HA HC-HB-HA MEAN 9.492 9.492 9.493 9.492 STANDARD DEVIATION

0.0046 0.0043 0.0042 0.0044

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Measurements of fuel pellets UO2 fuel pellet diameter and height measurements.

Measurements made with micrometer device (precision ±0,05 mm) in 1998

Table J-3: Pellet diameter measurements.

Pellets Height (mm) Diameter (mm) 1 14.85 7.85 2 14.90 7.85 3 15.00 7.90 4 15.00 7.90 5 14.95 7.85 6 15.00 7.90 7 15.00 7.90 8 15.00 7.85 9 15.00 7.90 10 15.00 7.90

Mean 14.97 7.88 Standard deviation (1σσσσ) 0.051 0.024

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Measurements made with palmer device (precision ± 0,05 mm) in 2000

Table J-4: Pellet diameter measurements.

Pellets Height (mm) Diameter (mm) 1 14.85 7.85 2 14.9 7.85 3 15 7.9 4 15 7.9 5 14.95 7.85 6 15 7.9 7 15 7.9 8 15 7.85 9 15 7.9 10 15 7.9 11 15.04 7.89 12 14.87 7.9 13 14.97 7.89 14 15.14 7.91 15 14.97 7.92 16 14.89 7.89 17 14.84 7.91 18 15.01 7.87 19 15 7.89 20 14.94 7.88 21 15.05 7.93 22 14.92 7.88 23 14.87 7.89 24 15.03 7.9 25 15 7.91 26 14.95 7.91 27 14.99 7.88 28 14.99 7.92 29 14.87 7.89 30 14.89 7.9 31 14.98 7.88 32 15.02 7.88 33 14.77 7.9 34 14.97 7.9 35 14.98 7.88 36 14.97 7.89 37 14.93 7.9 38 14.95 7.89 39 14.96 7.89 40 14.99 7.92

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Table J-4: Pellet diameter measurements (continued).

Pellets Height (mm) Diameter (mm) 41 14.91 7.89 42 14.98 7.9 43 14.97 7.89 44 15.04 7.91 45 / 7.9 46 / 7.91 47 14.97 7.88 48 14.89 7.87 49 14.91 7.9 50 14.86 7.88 51 14.96 7.89 52 14.85 7.89 53 14.85 7.87

Mean 14.954 7.8919 Standard deviation (1σσσσ) 0.068 0.017


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