Constituent migration model for fast reactor U-Pu-Zr metallic fuel

Conference · Tue Jan 01 04:00:00 EST 1991 · Transactions of the American Nuclear Society; (United States)

OSTI ID:5981231

Ishida, Masayoshi ^[1]; Ogata, Takanari; Kinoshita, Motoyasu ^[2]

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1. Hitachi Ltd. ERL, Ibaraki (Japan)
2. Central Research Inst. of Electric Power Industry, Tokyo (Japan)

The metallic fuel behavior of U-Pu-Zr has been actively investigated at Argonne National Laboratory. The Central Research Institute of the Electric Power Industry has been developing a metallic fuel liquid-metal fast breeder reactor concept jointly with several Japanese organizations. One of the development activities resulted in the fuel performance code SESAME. Recently, joint efforts have included the development of more mechanistic models for metallic fuel behavior. One of the models is for the constituent migration behavior in U-Pu-Zr fuels. For a simulation of constituent migration in the Experimental Breeder Reactor 2 (EBR-2) test pins ND30 and ND35, a quasi-binary U-Zr-(11.5 at.% Pu) phase diagram is produced using the U-Pu-Zr ternary phase diagram of O'Boyle and Dwight.

• OSTI ID: 5981231
• Report Number(s): CONF-910603--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 63
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
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ALLOY NUCLEAR FUELS
ALLOY SYSTEMS
ANL
BINARY ALLOY SYSTEMS
BREEDER REACTORS
DIAGRAMS
EBR-2 REACTOR
ELEMENTS
ENERGY SOURCES
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
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FUEL PINS
FUELS
FUNCTIONS
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NUCLEAR FUELS
PERFORMANCE
PHASE DIAGRAMS
PLUTONIUM
POWER REACTORS
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH PROGRAMS
RESPONSE FUNCTIONS
SODIUM COOLED REACTORS
SOLID FUELS
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US AEC
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