Published July 2000 | Version v1
Journal article Metadata-only

Evaluation of liquefaction temperature of metallic fuel for fast reactor. Study on liquefaction criteria using U-Pu/Fe diffusion couple

Creators

  • 1. Central Research Inst. of Electric Power Industry, Komae, Tokyo (Japan). Komae Research Lab

Description

In order to evaluate criteria for potential liquefaction at a metallic fuel-cladding interface, the reactions between U-xPu alloys (x=16, 22, and 25 at.%) and Fe at 650degC and 670degC have been examined. Liquid phase was observed in the reaction zone only for a U-22Pu/Fe couple annealed at 670degC. Comparison between the results of this study and a reported experiment on the U-PuZr/Fe system indicates that Zr content in the fuel alloy has little effect on liquefaction. The results also show that no liquid phase appears in the peripheral region of the metallic fuel pin below 650degC when the atom fraction ratio Pu/(Pu+U) in the fuel alloy is less than 0.25. (author)

Additional details

Publishing Information

Journal Title
Denryoku Chuo Kenkyusho Hokoku
Journal Issue
no.T99081
Journal Page Range
p. 1-4, 1-13
ISSN
1340-4652

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
32003858
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
ALLOY NUCLEAR FUELS; CHEMICAL REACTIONS; FBR TYPE REACTORS; FUEL-CLADDING INTERACTIONS; IRON; LIQUEFACTION; PHASE TRANSFORMATIONS; PLUTONIUM ALLOYS; RISK ASSESSMENT; TEMPERATURE DEPENDENCE; TEMPERATURE RANGE 0400-1000 K; URANIUM BASE ALLOYS
Descriptors DEC
ACTINIDE ALLOYS; ALLOYS; BREEDER REACTORS; ELEMENTS; ENERGY SOURCES; EPITHERMAL REACTORS; FAST REACTORS; FUELS; MATERIALS; METALS; NUCLEAR FUELS; REACTOR MATERIALS; REACTORS; SOLID FUELS; TEMPERATURE RANGE; THERMOCHEMICAL PROCESSES; TRANSITION ELEMENTS; URANIUM ALLOYS