Japan Atomic Energy Agency
Plutonium Fuel Development Facility
Masato KATO
Development of Np and Am bearing MOX fuels for Japan sodium cooled fast reactors
Fuel Technology R&D SectionPlutonium Fuel Development CenterNuclear Fuel Cycle Engineering LaboratoriesJapan Atomic Energy Agency
Fuel Technology R&D SectionPlutonium Fuel Development CenterNuclear Fuel Cycle Engineering LaboratoriesJapan Atomic Energy Agency
Masato KATO
Development of Np and Am bearing MOX fuels for Japan sodium cooled fast reactors
2
Plutonium Fuel Development Facility
---- Development of MOX containing MA ----
Hollow MOX pellets
Pellets of (Np0.02Am0.02Pu0.3U0.64)O2
Background
Specification of the fuel pelletType : Hollow type Pu content : 20 - 30%MA content : ~ 5%(Np+Am+Cm)Density : 95%TDO/M : <<<<1.97
1. Database and models for properties
2. Advanced fabrication process
3. Analysis code of irradiation behaviour of low O/M MA-MOX pellet
� Japan Atomic Energy Agency has developed homogeneous mixed oxide containing minor actinides (MA-MOX) for Japan sodium-cooled fast reactors.
Subjects to be carried out
3
Plutonium Fuel Development Facility
---- Development of MOX containing MA ----Background
1. Property Measurements・Thermodynamic data・Thermal properties・Chemical properties
2. Pellet Fabrication Test・Homogenization・O/M adjustment Technology・Sintering behavior
3. Irradiation test・Actinide redistribution・Microstructure change・FCCI
Experimental evaluation
1. Database and models for properties
2. Advanced fabrication process
3. Analysis code of irradiation behaviour of low O/M MA-MOX pellet
� Japan Atomic Energy Agency has developed homogeneous mixed oxide containing minoractinides (MA-MOX) for Japan sodium-cooled fast reactors.
Subjects to be carried out
4
Plutonium Fuel Development Facility
---- Development of MOX containing MA ----Background
1. Property Measurements・Thermodynamic data・Thermal properties・Chemical properties
2. Pellet Fabrication Test・Homogenization・O/M adjustment Technology・Sintering behaviour
3. Irradiation test・Actinide redistribution・Microstructure change・FCCI
Purpose of this workTo analysis PIE results by using the measured data to develop an analysis code.
Experimental evaluation� Japan Atomic Energy Agency has developed homogeneous mixed oxide containing minoractinides (MA-MOX) for Japan sodium-cooled fast reactors.
1. Database and models for properties
2. Advanced fabrication process
3. Analysis code of irradiation behaviour of low O/M MA-MOX pellet
Subjects to be carried out
5
Plutonium Fuel Development Facility
Contents1. Irradiation Test and PIE Results
2.Properties of the fuel pellets
3.Analysis of Irradiation behaviour
•Irradiation condition•Microstructure changes•Actinides redistribution•Evaluation of properties
Lattice parameter, Meting temperatureThermal conductivity, Oxygen potential
•O/M redistribution•Relation between Pu redistribution and vapour pressure•Evaluation of microstructure change
6
Plutonium Fuel Development FacilityIrradiation test
200m m
1500
mm
Fuel Pin
MA-MOX
MOX
Condition 1
Irradiation pattern
Held for 10min at 430W/cm
MA-MOX (Np0.016Am0.016Pu0.3U0.668)Oy 1.98MOX (Pu0.3U0.7)Oy 1.98
Composition O/M Pin No. Name
No.1-1
First Test
O/M=1.98
Pin No.1-1
MA-MOX
MOX
Time
7
Plutonium Fuel Development FacilityIrradiation test
Fuel Pins
MA-MOX
MOX
Second Test
O/M=1.98 , 1.96
MA-MOX (Np0.016Am0.016Pu0.3U0.668)Oy 1.98MOX (Pu0.3U0.7)Oy 1.98
Condition 2
Composition O/M
Irradiation pattern
Pin No.
200m m
1500
mm
Pin No.2-1
Pin No.2-1
Name
No.2-1
No.2-2 MA-MOX (Np0.016Am0.016Pu0.3U0.668)Oy 1.96MOX (Pu0.3U0.7)Oy 1.96
Held for 24h at 430W/cm
8
Plutonium Fuel Development FacilityPIE Results Microstructure Change
No.1-1 MA-MOX, O/M=1.98, at 427W/cm for 10 min
1.The heat rate of the fuels attained about 430W/cm.
2.The pellets were unmelted.
3.Pores migrated to the center.
4.Columnar grain and central void were observed
Central voidColumnar grain
Central void
Columnar grain
Central voidColumnar grain
Observation results
No.2-1 MA-MOX, O/M=1.98, at 432W/cm for 24h
No.2-2 MA-MOX, O/M=1.96, at 429W/cm for 24h
9
Plutonium Fuel Development Facility
0
1000
2000
3000
4000
5000
6000
7000
8000
0.0 0.5 1.0 1.5 2.0 2.5Radius(mm)
Pu (c
ount/
sec)
0
200
400
600
800
1000
1200
1400
Am, N
p (co
unt/s
ec)
PuAmNp
Central void
0
1000
2000
3000
4000
5000
6000
7000
8000
0.0 0.5 1.0 1.5 2.0 2.5Radius(mm)
Pu (c
ount/
sec)
0
200
400
600
800
1000
1200
1400
Am, N
p (co
unt/s
ec)
PuAmNp
Central void
Actinide Redistribution
1.The content of Puand Am increased at pellet center.
2.The increment of Pu and Am decreased with decreasing O/M.
3.The contents of Npand U were flat.
Observation results
No.2-1 MA-MOX, O/M=1.98, at 432W/cm for 24h
N0.2-2 MA-MOX, O/M=1.96, at 429W/cm for 24h
PuAm
Np
Pu
AmNp
PIE Results
10
Plutonium Fuel Development Facility
Lattice Parameter
5.40
5.42
5.44
5.46
5.48
5.50
1.80 1.85 1.90 1.95 2.00 2.05
B
C
MOX
MA-MOX
Lattic
e para
meter
; a (A
)
O/M
o
(U
1-y
Pu
y
)O
2.00
(U
0.96-y
Pu
y
Am
0.02
Np
0.02
)O
2.00
Properties of fuel pellets (1/4)
Lattice Parameter vs. O/M ratio
1.The model to represent the lattice parameter was derived.
2.MA content slightly caused the lattice parameters to decrease.
3.The difference of theoretical density is 0.01-0.02g/cm3.
Results
))112.01((3/4 ac rxra ++=)"')"'1(( yryrzryyzrr NpAmPuUc +++−−−=
M.Kato, et al.,J.N.M.385 (2009) 117
11
Plutonium Fuel Development Facility
Melting Temperature
3000
3020
3040
3060
3080
3100
0 1 2 3 4
Temp
eratur
e (K)
3000
3020
3040
3060
3080
3100
0 0. 0. 0. 0. 0. 0. 0 . 0.
3000
3020
3040
3060
3080
3100
0 0. 0. 0. 0. 0. 0. 0. 0.
Am+Np content (Am/Np=1)2.00
1.98O/M
Liquidus
1.96Solidus
Properties of fuel pellets (2/4)
Variation of Solidus and Liquidus Temp.
1.The data were measured and analyzed by the ideal solid solution model.
2.MA content caused to decrease by 2-3K /%MA.
3.The solidus temperature of MA-MOX is over 3000K.
Results
M.Kato, et al.,ICAPP ‘09
12
Plutonium Fuel Development FacilityProperties of fuel pellets (3/4)
0
1
2
3
4
5
0 500 1000 1500 2000 2500
BCDE
Therm
al co
nduc
tivity
;λ0(W
/mK)
Temperature (K)
MOXMA-MOX
O/M=1.98
O/M=1.96
Thermal conductivity
1.The data were measured as functions of MA content, density, O/M and temperature.
2.MA content caused to decrease slightly in temperatures of less than 1000K.
Results
Thermal conductivity
( ) ( ) Txx 42- 2
2-1
1-0 10493.22.625-101.595 z106.317 z103.583 2.7131
−×++×+××+××+=λ
××+
TT
4
2/5
11 10522.1exp10541.1
z1: Am contentz2: Np content x:Deviation x in MO2-x
M.Kato, et al., OECD/NEA, Oct. 6-10, 2008, Japan
13
Plutonium Fuel Development FacilityProperties of fuel pellets (4/4)
-700
-600
-500
-400
-300
-200
1200 1400 1600 1800 2000
CDBC
Oxyg
en po
tentia
l (kJ/m
ol)
Temperature (K)
O/M=1.98
O/M=1.96
MOX
MA-MOX
Oxygen potential
Oxygen potential
1.The data were measured by gas equilibrium method.
2.MA content caused the oxygen potential to increase slightly.
Results
M.Kato, et al.,J.N.M. 385 (2009) 419
14
Plutonium Fuel Development FacilityProperties of fuel pellets (4/4)Oxygen potential
1.The data were measured by gas equilibrium method.
2.MA content caused the oxygen potential to increase slightly.
Results
Oxygen potential
SummaryThe effect of MA addition on the properties is negligibly small in the operation temperature range of FR fuels
-700
-600
-500
-400
-300
-200
1200 1400 1600 1800 2000
CDBC
Oxyg
en po
tentia
l (kJ/m
ol)
Temperature (K)
O/M=1.98
O/M=1.96
MOX
MA-MOX
15
Plutonium Fuel Development Facility
Analysis ProcedureInput
Vapour pressure
Thermal conductivity
Lattice parameter
-Vapour pressure-Oxygen potential
Results- Temperature- O/M ratio
TemperatureO/M redistribution
Migration rate of pore2.Relation between vapourpressure and Pu redistribution
3.Evaluation of microstructure change
1.Comparison with Melting temperature
Analysis of irradiation behaviour
DimensionDensityO/M ratioLinear heat rateCoolant temperature
16
Plutonium Fuel Development Facility
Input
Vapour pressure
Lattice parameter
-Vapour pressure-Oxygen potential
Results- Temperature- O/M ratio
TemperatureO/M redistribution
Migration rate of pore2.Relation between vapourpressure and Pu redistribution
3.Evaluation of microstructure change
1.Comparison with Melting temperature
Analysis Procedure
Thermal conductivity
DimensionDensityO/M ratioLinear heat rateCoolant temperature
17
Plutonium Fuel Development Facility
Thermal conductivity
DimensionDensityO/M ratioLinear heat rateCoolant temperature
Input
Vapour pressure
Lattice parameter
-Vapour pressure-Oxygen potential
Results- Temperature- O/M ratio
TemperatureO/M redistribution
Migration rate of pore2.Relation between vapourpressure and Pu redistribution
3.Evaluation of microstructure change
1.Comparison with Melting temperature
Analysis Procedure
18
Plutonium Fuel Development Facility
Input
Vapour pressure
Migration rate of pore
Lattice parameter
-Vapour pressure-Oxygen potential
Results- Temperature- O/M ratio
2.Relation between vapourpressure and Pu redistribution
3.Evaluation of microstructure change
TemperatureO/M redistribution
1.Comparison with melting temperature
Analysis Procedure
Thermal conductivity
DimensionDensityO/M ratioLinear heat rateCoolant temperature
19
Plutonium Fuel Development Facility
Input
Vapour pressure
Thermal conductivity
Lattice parameter
-Vapour pressure-Oxygen potential
Results- Temperature- O/M ratio
TemperatureO/M redistribution
Migration rate of pore2.Relation between vapourpressure and Pu redistribution
3.Evaluation of microstructure change
1.Comparison with Melting temperature
Analysis ProcedureDimensionDensityO/M ratioLinear heat rateCoolant temperature
20
Plutonium Fuel Development Facility
O/M Redistribution
1.80
1.85
1.90
1.95
2.00
2.05
0.0 0.5 1.0 1.5 2.0 2.5 3.0
O/M=1.98O/M=1.96O/M=1.98O/M=1.96
O/M
Distance from cladding inner surface (mm)
Sari's modelAitken's model
O/M ratio distribution in the radial direction
Results 1.Both models gave
almost the same result in high O/M pellets.
2.The results of low O/M pellets differed according to models.
3.Sari’s model was employed.
21
Plutonium Fuel Development Facility
10
-5
10
-4
10
-3
10
-2
10
-1
10
0
10
1
0.0 0.5 1.0 1.5 2.0 2.5 3.0
O/M=1.98
O/M=1.96
P (Pu
-spec
ies)/P
(U-sp
ecies
)
Composition of the pellet
Distance from cladding inner surface (mm)
Evaluation of vapour pressure
Variation of vapor pressure
10-35
10-30
10-25
10-20
10-15
10-10
10-5
0.0 0.5 1.0 1.5 2.0 2.5 3.0
UUOUO2UO3PuPuOPuO2AmO2AmO
Vapo
ur pre
ssure
(atm
)
Distance from pellet surface(mm)
Variation of Pu-/U- species
Result1.Variation of vapor pressure ratio of Pu/U-species
was evaluated using Rand –Markin model.
22
Plutonium Fuel Development Facility
Evaluation of Pu redistribution
0.1 1.0 10.0
0
5
10
15
20
MOX
MA-MOX
MOX
MA-MOX
F
MOX
MA-MOX
MOX
MA-MOX
PPu-species/PU-species ratio
Amount of Pu increase (wt%)
O/M=1.98
O/M=1.96
Composition of the pellet
Sari's model
: Pu/U ~ 0.3/0.7
U increasePu increase
0.4
Result1.Calculation result shows that U content increases
at pellet center.
23
Plutonium Fuel Development Facility
0.1 1.0 10.0
0
5
10
15
20
MOX
MA-MOX
MOX
MA-MOX
F
MOX
MA-MOX
MOX
MA-MOX
PPu-species/PU-species ratio
Amount of Pu increase (wt%)
O/M=1.98
O/M=1.96
Composition of the pellet
Sari's model
: Pu/U ~ 0.3/0.7
U increasePu increase
?
Evaluation of Pu redistribution
0.4
ExpectationIncrement of Pu should be increased with decreasing the PPu-species/PU-species.
24
Plutonium Fuel Development Facility
0.1 1.0 10.0
0
5
10
15
20
MOX
MA-MOX
MOX
MA-MOX
F
MOX
MA-MOX
MOX
MA-MOX
PPu-species/PU-species ratio
Amount of Pu increase (wt%)
O/M=1.98
O/M=1.96
Composition of the pellet
Sari's modelO/M=1.98
O/M=1.96
Author's correction
: Pu/U ~ 0.3/0.7
U increasePu increase
Evaluation of Pu redistribution
Results1.Calculation results show that Pu content increase at pellet centre.
2.Two lines were obtained depending on O/M ratio.
0.4
O/M=1.96O/M=1.98
25
Plutonium Fuel Development Facility
Reviewing of the model for O/M redistributionSari’s model for O/M redistribution
−∗=
122
1 11ln TTRQ
xx
2455 105.81066.51045.9 PuPu VVQ ×−×+×−=∗
X: deviation in (U,Pu)O2-xT: temperatureR :gas constant,Q* :::: the molar effective heat of transport VPu : Pu valence
0
10000
20000
30000
40000
3.23.43.63.84.0
C
D
-Q
*
(cal/mol)
V
Pu
Sari's model
This work
Evaluation of equation for Q*
Calculation of O/M Redistribution, temperature and vapour pressure
Evaluation of the relationship between the PPu-species/PU-speciesand the Pu increase
Corrected Eq.352666 107122.1107705.1101012.61001.7 PuPuPu VVVQ ×−×−×+×−=∗
26
Plutonium Fuel Development Facility
Sari’s model for O/M redistribution
−∗=
122
1 11ln TTRQ
xx
2455 105.81066.51045.9 PuPu VVQ ×−×+×−=∗
X: deviation in (U,Pu)O2-xT: temperatureR :gas constant,Q* : the molar effective heat of transportVPu : Pu valence
Evaluation of equation for Q*
Calculation of O/M Redistribution, temperature and vapour pressure
Evaluation of the relationship between the PPu-species/PU-speciesand the Pu increase
Reviewing of the model for O/M redistribution
Corrected Eq.352666 107122.1107705.1101012.61001.7 PuPuPu VVVQ ×−×−×+×−=∗
0.1 1.0
0
5
10
15
20
PPu-species/PU-species ratio
Amount of Pu increase (wt%)
Composition of the pellet
Sari's model
Author's correction
27
Plutonium Fuel Development Facility
Calculation results in MA-MOX pellets
1000
1500
2000
2500
3000
0.0 0.5 1.0 1.5 2.0 2.5 3.0
O/M=1.98O/M=1.96
Temp
eratur
e (K)
Distance from cladding inner surface (mm)
(a) Temperature
1.90
1.95
2.00
2.05
0.0 0.5 1.0 1.5 2.0 2.5 3.0
O/M=1.98O/M=1.96
O/M
Distance from cladding inner surface (mm)
(b) O/M ratio
0.0
1.0
2.0
3.0
4.0
5.0
0.0 0.5 1.0 1.5 2.0 2.5 3.0
O/M=1.98O/M=1.96
Therm
al co
nduc
tivity
(W/cm
K)
Distance from cladding inner surface (mm)
(c) Thermal conductivity
10-310-210-1100
101
102
0.0 0.5 1.0 1.5 2.0 2.5 3.0
O/M=1.98O/M=1.96P (
Pu-sp
ecies
)/P(U
-spec
ies)
Composition of the pellet
Distance from cladding inner surface (mm)
(d) Vapour pressure ratio
Temperature Thermal conductivity
O/M ratio Vapour pressure ratio of Pu-/U-species
28
Plutonium Fuel Development Facility
3.0
3.2
3.4
3.6
3.8
4.0
2000 2200 2400 2600 2800 3000
MOXMA-MOXMOXMA-MOX
Diam
eter o
f colu
mnar
grain
region
(mm)
Temperature at pellet center (K)
O/M=1.98O/M=1.96
0.0
0.5
1.0
1.5
2000 2200 2400 2600 2800 3000
MOXMA-MOXMOXMA-MOX
Diam
eter o
f cen
tral v
oid (m
m)
O/M=1.98O/M=1.96
Temperature at pellet centre (K)
Central voidColumnar grain
Results1.The both region grew with temperature.2.The central void of high O/M pellet is larger than
that of low O/M pellets.
Columnar grain region Central void
Microstructure change
O/M=1.96O/M=1.98
29
Plutonium Fuel Development Facility
Summary1.The physical properties of the Np/Am-MOX were evaluated, and the effect of Np/Am addition was negligiblyyyy small.
2.The relation between the Pu redistribution and the vapor pressure was described by correcting Sari’s model for O/M redistribution.
3.The low O/M pellet attained higher temperature, however, the diameter of the central void was small as compared with the high O/M pellet.
4. It is needed to measure experimental data and to derive advanced models for describing irradiation behavior of low O/M fuel.
Japan Atomic Energy Agency
Plutonium Fuel Development Facility
Masato KATO
Development of Np and Am bearing MOX fuels for Japan sodium cooled fast reactors
Fuel Technology R&D SectionPlutonium Fuel Development CenterNuclear Fuel Cycle Engineering LaboratoriesJapan Atomic Energy Agency
Fuel Technology R&D SectionPlutonium Fuel Development CenterNuclear Fuel Cycle Engineering LaboratoriesJapan Atomic Energy Agency
Masato KATO
Development of Np and Am bearing MOX fuels for Japan sodium cooled fast reactors