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U.S. Department of Energy
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LIQUID METAL DECANNING OF HIGHLY IRRADIATED UO$sub 2$--PuO$sub 2$/STAINLESS STEEL CLAD FUELS.

Technical Report ·
OSTI ID:4707169
A decanning process for fast breeder fuels of the UO{sub 2} - PuO{sub 2}/stainless steel type was investigated. The method is based on a selective dissolution of the stainless steel cladding material in a liquid metal solvent composed of Sb-Cu at temperatures betwen 800 and 950 deg C. The stainlesss steel dissolution rates, which vary between 40 and 60 wt%, are strongly temperature dependent. The crucible is graphite. The fuel UO{sub 2} - PuO{sub 2} is separated from the liquid solvent by filtration. Microprobe examinations showed that after solidification the structure of the solvent alloy including stainless steel is rather uniform. The liquid metal dissolution process offers advantages over mechanical or chemical decladding methods, particularly for highly irradiated fuels. The presence of Na would not be of great concern since Na is slightly soluble in the Sb-Cu alloy. The dissolution can be performed without disassembly of the fuel element. The fission gases are evacuated and condensed in a minimum volume. The whole decanning process can be carried out with very compact equipment located on the reactor site. (auth)
Research Organization:
European Communities, Brussels (Belgium). Commission. European Atomic Energy Community, Ispra (Italy). Joint Nuclear Research Center
NSA Number:
NSA-26-020183
OSTI ID:
4707169
Report Number(s):
IAEA--115
Country of Publication:
IAEA
Language:
English