Japan Atomic Energy Agency Plutonium Fuel Development Facility Experimental Evaluation of Am and Np Bearing Mixed Oxide Fuel Properties M. Kato, K. Morimoto, A. Komeno, S. Nakamichi, M. Kashimura Nuclear Fuel Cycle Engineering Laboratories, Japan Atomic Energy Agency
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Experimental Evaluation of Am and Np Bearing Mixed Oxide ... · 05 10 15 MA Content (%) 29%Pu 40%Pu. Am/Np-MOX Np-MOX Am-MOX Calculation Am/Np-MOX Np-MOX Am-MOX Experiment o Lattice
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Japan Atomic Energy Agency
Plutonium Fuel Development Facility
Experimental Evaluation of Am and Np Bearing
Mixed Oxide Fuel Properties
M. Kato, K. Morimoto, A. Komeno, S. Nakamichi, M. Kashimura
Nuclear Fuel Cycle Engineering Laboratories, Japan Atomic Energy Agency
Plutonium Fuel Development Facility
- Development of MOX containing MA -
Japan Atomic Energy Agency has developed homogeneous mixed oxide containing minor actinides (MA-MOX) as a fuel of the advanced fast reactor.
Specification of the fuel pelletType : Hollow type Pu content : 20 - 30%MA content : - 5%(Np+Am+Cm)
Density : 93%TDO/M : 1.95Burn-up : 150GWd/t
Hollow pellets of MOX
Pellets of (Np0.02Am0.02Pu0.3U0.64)O2
Background
Physical property measurements of Am and Np bearing MOXThe effect of MA addition on the physical properties
Plutonium Fuel Development Facility
Outline
Sample preparation
Phase state and Phase separation
Lattice parameters
Oxygen potentials
Melting temperatures
Thermal conductivities
Plutonium Fuel Development Facility
Sample preparation
Ball mill
Starting materials
Press
Sintering
Annealing for MO2.00
Annealing to adjust O/M ratio
Measurement
UO2, (U,Pu)O2, (U,PuNp)O2, (Pu,Am)O2
at 1923-1973K for 3-4 h in 5%H2/Ar flowing gas added moisture
at 1123K for 4 h in the atmosphere of ΔG=-400-420kJ/mol
at 1123-1973K for 3-25 h in an appropriate atmosphere
ρ : Density of specimenρth : Theoretical density of specimen
( )( )p
pF×+
−=
β11
F : Maxwell-Eucken equation
β =0.5
Plutonium Fuel Development Facility
1
2
3
4
5
6
800 1000 1200 1400 1600 1800Temperature (K)
Ther
mal
con
duct
ivity
(W/m
/K) 6%Np-MOX
12%Np-MOX0.7%Am-MOX 2%Am-MOX3%Am-MOX
1.0
2.0
3.0
4.0
5.0
6.0
0% 2% 4% 6% 8% 10% 12% 14%Th
erm
al c
ondu
ctiv
ity (W
/m/K
)Np content (%)
1073
1273
1473
1.0
2.0
3.0
4.0
5.0
6.0
0% 1% 2% 3% 4%Am content (%)
Ther
mal
con
duct
ivity
(W/m
/K)
TC/1073KTC/1273KTC/1473KTC/1673K
KK
K
O/M=2.00
Effect of MA content
The addition of MA caused to decrease slightly the thermal conductivities in the temperature range of less than 1000K.
Thermal conductivity
Plutonium Fuel Development Facility
The thermal conductivities decrease significantly with decreasing O/M ratio.The equation was derived as functions of temperatures, MA contents and O/M ratios.
It is expected that the equation will be revised by expanding data in the high temperature region.
0.0
1.0
2.0
3.0
4.0
5.0
800 1200 1600 2000 2400Temperature (K)
Ther
mal
con
duct
ivity
(W/m
/K)
O/M=2.00 O/M=1.944 O/M=1.919
O/M=1.945 O/M=1.923
Effect of O/M ratio
( ) ( ) 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
Thermal conductivity
Plutonium Fuel Development Facility
The physical properties, lattice parameters,phase diagram, oxygen potentials, meltingtemperatures and thermal conductivities, ofAm and Np-bearing MOX were measured.The effects of MA addition on the physicalproperties are small. No MA addition affectsfuel properties significantly.We obtained the basic data for conducting theirradiation tests of MA-bearing MOX fuel.
Summary
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Plutonium Fuel Development Facility
The expected phase diagram in U-Pu-O ternary system The effect of O/M ratio
Melting Temperatures
2800
2900
3000
3100
3200
1.7 1.8 1.9 2 2.1
UO211.8%Pu20%Pu39%Pu46%PuPuO2-X
Tem
pera
ture
(K)
O/M
Solidus calculated in this work
11.8%Pu
20%Pu
39%Pu
46%Pu
UO
2±X L
3000K
2500K
2000K
Pu0.2 U
0.8 O2 ±X
Pu0.1 U
0.9 O2±X
O/M=2.0
O/M=1.5
Limit of hypo-stoichiometric composition
Maximum melting temperature
Limit of hyper-stoichiometric composition
L30
00K
2500
K
2000
K
PuO 2-
x
Pu0.4 U
0.6 O2±X
PuO1.7-UO2
Effect of O/M ratio
Plutonium Fuel Development Facility
0 0.1 0.2 0.3 0.4 0.5 0.6
AmO 2
PuO2
0.1
0.2
0.3
0.4
0.5
at 2980K
0
UO2
Liquid
Solid
0.6
Solid+
Liquid
Database and Models
Modeling
Thermal conductivity
Lattice parameter
Oxygen potential
Melting temperature
1.85 1.9 1.95 2 2.05 2.110-25
10-20
10-15
10-10
10-5
1373 K1473 K1573 K1623 K1623 K1373 K1473 K1573 K1623 K