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Performance of ferritic alloy cladding in LMR (liquid metal reactor) mixed-oxide fuel pins in EBR-II

Conference ·
OSTI ID:6890736
Mixed uranium-plutonium oxide fuel pins with candidate ferritic alloy cladding have been irradiated in the EBR-II to evaluate performance for possible Liquid Metal Reactor (LMR) application. Ferritic alloys are of considerable interest in LMR's because of their resistance to irradiation induced swelling which, in the case of austenitic alloys, has led to duct dimensional changes and interactions between the duct and pin bundle. Ferritic alloys may also possess improved resistance to environmentally assisted crack propagation when compared to austenitic alloys.
Research Organization:
Hanford Engineering Development Lab., Richland, WA (USA)
DOE Contract Number:
AC06-76FF02170
OSTI ID:
6890736
Report Number(s):
HEDL-SA-3542-FP; CONF-861102-38; ON: DE87005473
Country of Publication:
United States
Language:
English