STATUS OF ENEA ACTIVITIES RELATED TO COOL …€¦ · GAMBIT SALOME LIBMESH LASPACK PARAVIEW...

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Reactor and Fuel Cycle Safety and Security Methods SectionItalian National Agency for New Technologies, Energy and Sustainable Economic Development

P. Meloni [email protected]

STATUS OF ENEA ACTIVITIES RELATED TO COOL INPRO PROJECT

INPRO COOL Project 3rd Consultancy Meeting Vienna, 22-23 June, 2009

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NUCLEAR FUSION AND FISSION, AND RELATED TECHNOLOGIES DEPARTEMENT Italian National Agency for New Technologies, Energy and the Environment

ENEA’s Contribute to the COOL Collaborative Project of INPRO

HEAVY LIQUID METALS (LBE & LEAD)• 2.1 Experimental and computational studies on correlations for LM for tubular,

pebble bed and other geometries� Comparative assessment of empirical correlations for single-phase heat transfer in

rod bundles of HLM cooled reactors• 2.4 Assessment of existing pressure drop and heat transfer correlations for

natural circulation flow� Assessment of RELAP5 pressure drop correlations for HLM systems � Natural and Gas Enhanced Circulation Tests in the NACIE Loop

• 2.5 Assessment of existing pressure drop and heat transfer correlations for enhanced gas injected circulation� Investigation of reliability of gas-enhanced circulation on CIRCE facility

• 3.1 Verification of CFD calculation models for lower temperatures for LM � CFD simulation of square core channel

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ENEA’s Contribute to the COOL Collaborative Project of INPRO

• 5.3 Development of technologies and tools (sensors, detectors, instruments and software) for measurement and control of impurities� Development of oxygen control process and assessment of instrumentation

techniques • 6.1 Experimental studies on components and various materials that are in contact

during operation with LM and MS� Identification and testing of the most promising alloys as candidate material for

pump impeller� Design and assessment of heat exchangers for DHR (Decay Heat Removal)

Systems in HLM reactors

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Section 2.1 : Comparative assessment of empirical correlations for single-phase heat transfer in rod bundles of HLM cooled reactors

Nu = 5.0 + 0.025∗Pe 0.8

Nu = 7.55∗(P/D) - 20∗(P/D)-13 + 0.040778∗(P/D) -2 ∗Pe (0.56 + 0.19∗(P/D))

Nu = 7.55∗(P/D) - 14∗(P/D)-5 + 0.007∗Pe (0.64 + 0.246∗(P/D))

� Seban-Shimazky correlation for convective heat transfer inside pipe

� Subbotin-Ushakov correlation in simplified form (P/D > 1.2) for convective heat transfer in triangular bundle geometry

� Zhukov correlation without spacers for convective heat transfer in square bundle geometry

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Section 2.1 : Work in Progress

� Assessment of correlations in the RELAP5 code on NACIE natural circulation and gas enhanced tests (see section 2.4)

Section 2.1 : Future Work

� Assessment of correlations in RELAP5 code on NACIE bundle tests� Verification of RELAP5 on ICE tests

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Section 2.4 : Assessment of RELAP5 pressure drop correlations for HLM systems on HELIOS tests (LACANES Benchmark)

� Results of the first phase of the benchmark (forced convection)• Calculation showed an underestimation of pressure drop in complex component

(core) and overestimation in valve using pressure drop coefficient provided by the manufacturer

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� Re-calibration of the pressure drop coefficients for the second phase (natural convection)

0.196019.691810.20213.57Tuned calculation

0.8975.17899.850713.57Blind calculation

ValveCore gridOrificeK valueMass Flow

Rate(kg/s)

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� Preliminary calculation of the loop in natural convection

Pw

Pw

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� Available experimental characterization of the pressure drops through the core, orifice and gate valve allowed to assess the corresponding RELAP5 modeling

Core pressure drop Vs mass flow

Orifice pressure drop Vs mass flow Valve pressure drop Vs mass flow

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Section 2.4 : Natural and Gas Enhanced Circulation Tests in the NACIE Loop

� Experimental tests of natural and gas enhanced circulation conducted in 2009• Tests provided data of convective thermal

exchange for a single pin

Cover Gas Inlet

Cover Gas Outlet

Gas Injection

Heat Exchanger

Water Outlet

Water Inlet

Ultrasonic Flow Meter

Heat Source

Expansion Vessel

Riser

Downcomer

Cover Gas Inlet

Cover Gas Outlet

Gas Injection

Heat Exchanger

Water Outlet

Water Inlet

Ultrasonic Flow Meter

Heat Source

Expansion Vessel

Riser

Downcomer0.0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0 5000 10000 15000 20000 25000 30000

Time [s]

LBE

veloc

ity [m

/s]

0.0E+00

2.0E+04

4.0E+04

6.0E+04

8.0E+04

1.0E+05

1.2E+05

1.4E+05

Reyn

olds N

umbe

rwRe

0.00

0.05

0.10

0.15

0.20

0.25

0.30

0 5000 10000 15000 20000 25000 30000

Time [s]

LBE

veloc

ity [m

/s]

0.0E+00

1.0E+04

2.0E+04

3.0E+04

4.0E+04

5.0E+04

6.0E+04

Reyn

olds N

umbe

rwRe

Gas Enhanced Circulation

Natural Circulation

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� Assessment of the HLM dedicated version of RELAP5 is in progress (cooperation with University of Pisa)

RELAP5 NACIE Nodalization

Gas Enhanced Circulation: LBE Mass Flow

PIPE 10

PIPE 20

SNGLVOL 30

PIPE 70

PIPE 100

PIPE 130

PIPE 160 PIPE

170

PIPE180

PIPE 190

PIPE 200

TMDPVOL 300

TMDPVOL 320

PIPE 310

SNGLVOL 150

PIPE 230

PIPE 220

BRANCH 210

SNGLVOL 80

SNGLVOL 90

Separator 110

SNGLVOL 40

BRANCH 50

TMDPVOL 120

TMDPVOL 60

140

J-225

J-25

J-35

J-75

J-95

J-195

J-185

J-175

J-165

J-315

TMDPJUN 305

J-85

J-15

Heater section

HX LBE side

HX Water side

TMDPJUN 55

FPS

0

5

10

15

20

25

30

0 10000 20000 30000 40000Time [s]

LBE F

low R

ate [k

g/s]

Energy BalanceCalculated

200220240260280300320340360380

0 10000 20000 30000 40000Time [s]

Temp

eratur

e [°C

]

T_in (experimental) T_out (experimental)T_in (calculated)T_out (calculated)

Gas Enhanced Circulation: Inlet/Outlet LBE Temperatures

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� Assessment of RELAP5 pressure drop correlations for HLM systems on HELIOS tests (LACANES Benchmark): Participation in the second phase of the benchmark (natural convection)

� Natural and Gas Enhanced Circulation Tests in the NACIE LoopInstallation of a bundle suitably instrumented for convective heat transfer investigation

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Section 2.5 : Investigation of reliability of gas-enhanced circulation in CIRCE facility

� Characterization of gas-enhanced circulation in CIRCE completed

� Assessment of existing pressure drop and heat transfer correlations both for natural circulation and for gas-enhanced circulation conducted in parallel (see section 2.4)

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Section 3.1 : CFD simulation of square core channel

� CFD simulation of Lead Square Unwrapped Lattice Core• Capability to simulate the whole core behavior taking into account the

intermingled effects among assembly flows• Full three-dimensional incompressible Navier-Stokes and energy equations

at a coarse, assembly length level and linked to the fine, sub-channel level state through transfer operators based on parametric coefficients that summarize local fluctuations.

• The overall effects among assembly flows are evaluated by using average assembly turbulent viscosity and energy exchange coefficients estimated with CFD simulations over limited subassembly regions

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� Two level approach

FineLevel

CoarseLevel

Solution of the DNSNavier-Stokes

equations

Solution of thelumped parameter

equations

Transfer operator based on parametric coefficients to summarize local fluctuations

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� 3D FEM Code

1 Finite Element Discretization2 Multigrid Solver

3 Object Oriented (Modularization)

MESHGENERATION

CORE

POSTPROCESSING

GAMBIT SALOME

LIBMESH LASPACK

PARAVIEW SALOME

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� Comparison between independent channel models (RELAP5) and 3D model of the ELSY (European Lead System) Core (three fuel zone)

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� Investigation of the effect of non-uniform pressure boundary conditions in lower and upper plenum on the temperature distributionParabolic axisymmetric outlet pressure distribution to take into account pumps locations and upper plenum structure → velocity field changes direction and magnitude inside the core and the outflow temperature profile differs substantially

50556065707580859095

1 2 3 4 5 6 7 8FA Ring

Core

DT (°

C)

RELAP53D Model

504,1 504,9 495,1 482,8495,9 495,3 493,2486,4 484,0 474,5

499,6 503,3 503,7 500,3483,7

504,3 499,5 499,6 502,0 498,3500,7 505,1 501,2 505,1

506,2 501,1501,5 508,3 510,1 516,2 518,0 492,8501,4 500,7 501,4 505,2

504,4 506,4 513,2 505,0 491,7502,4 502,8 503,9 505,7 506,2 504,4 501,5502,2 502,8

502,0501,7 503,0 504,7 511,1 503,3 491,1

513,8 514,7501,9 503,3 505,8 506,0 504,5

500,2 501,1 503,2 505,2 517,4 484,4500,5 501,4 503,8 506,6 507,1 507,2 507,9 501,0

504,4 507,4 510,4 520,4 508,0499,9 501,9 506,1 508,1 508,9 509,2 506,1499,3 501,6

Clad Peak Temperature

RELAP5

3D MODEL

Lead Temperature at Core Outlet

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� Implementation and validation of a suitable turbulence model in 3D FEM code Use of rod bundle available data (KALLA) and future data (NACIE)

� Development of 3D Model of Lead Square Unwrapped Lattice Core (porous media) plus Upper and Lower Plenums (open CFD media) Benchmarking with alternative codes

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Section 5.3 : Development of oxygen control process and assessment of instrumentation techniques

� The manufacturing, implementation and validation of Oxygen sensors in a pool device like CIRCE successfully achieved.

� Next challenge will be the study of the sensors’ behavior when coupled with chemistry active control systems (activity not planned yet)

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Section 6.1 : Identification and testing of the most promising alloys as candidate material for pump impeller

� MAXTHAL (Ti3SiC2), a ternary compound that combines proprieties of ceramics with those of metals has been tested in the Lead loop CHEOPE III:• Good corrosion resistance in fluent pure lead• Formation of a thin oxide layer hypothesized ( positive mass gain for each

specimen and presence of oxygen the first micron)• no dissolution of Ti3SiC2 have been observed in three specimens analyzed

by Scanning Electron Microscopy (SEM)• none pure Lead penetration inside the Ti3SiC2 matrix through open

porosities after first microns

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Section 6.1 : Design and assessment of heat exchangers for DHR (Decay Heat Removal) Systems in HLM reactors

� Innovative Heat Exchanger (W-DHR) designed, manufactured and installed in the CIRCE facility (ICE Experiment)

Heat Exchanger

Cover Head

Riser

Dead Volume

Fitting Volume

Flow Meter

Feeding Conduit

Insulation Volume

CIRCE main vessel (S100)

Coupling Flange

FPS

Heat Exchanger

Cover Head

Riser

Dead Volume

Fitting Volume

Flow Meter

Feeding Conduit

Insulation Volume

CIRCE main vessel (S100)

Coupling Flange

FPS

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� ICE Experimental Program including steady state and transient tests was completed in first part of 2009. • Analysis of the experimental results in progress• The inlet and outlet temperature trends trough the HS(FPS) and HX

highlight that a thermal exchange takes place along the LBE stream line (interaction downcomer-test section, losses toward the environment )

250

270

290

310

330

350

370

390

410

430

450

0 2000 4000 6000 8000Time [s]

Temp

eratur

e [°C

]

Tin HS Tout HS

Tin HX Tout HX

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� Erosion characterization of Ti3SiC2 at high relative lead speed to confirm as potential material for the pump impeller and bearing of mechanical pumps working in leadNeed of a dedicated facility to test prototypical impellers

� Further experimental campaign is planned in CIRCE to complete assessment of the innovative DHR systemPlanned in the next year

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Summary

CFD model extended to all core

CFD simulation of square core channel

3.1

CompletedInvestigation of reliability of gas-enhanced circulation on CIRCE facility

2.5

Tests completedRELAP validation in progress

Natural and Gas Enhanced Circulation Tests in NACIE

On progress to be completed next year

Assessment of RELAP5 pressure drop correlations …2.4

CompletedValidation in 2.4

Comparative assessment of empirical correlations..

2.1StatusActivitySection

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Summary

Tests completedAnalysis in progress

Design and assessment of heat exchangers …

Completed in this phaseFuture activity to be defined

Identification and testing of the most promising alloys …6.1

Completed in this phaseFuture activity to be defined

Development of oxygen control process….

5.3StatusActivitySection

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