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Title: Development of new ferritic cladding materials for metal-fueled FBRs

Conference · · Transactions of the American Nuclear Society; (United States)
OSTI ID:6683693
;  [1]; ;  [2]
  1. Central Research Institute of the Electric Power Industry, Tokyo (Japan)
  2. Kobe Steel, Tokyo (Japan)

It is well known that the characteristics of metallic fuel (U-Zr, U-Pu-Zr alloy), such as high fissile density, high thermal conductivity, and harder neutron spectrum, enable the development of superior core performance and safety features based on the passive safety design of a liquid metal fast breeder reactor (LMFBR). For the higher performance of a metal fuel core, higher-strength and high-swelling-resistant cladding materials are required. Ferritic stainless steel is well known to be resistant to swelling up to very high fast neutron fluence, but the creep strength is not sufficient for the practical use as a cladding material. In this study, combinations of various strengthening techniques were applied to Fe-12% Cr ferritic stainless steels.

OSTI ID:
6683693
Report Number(s):
CONF-921102-; CODEN: TANSAO
Journal Information:
Transactions of the American Nuclear Society; (United States), Vol. 66; Conference: Joint American Nuclear Society (ANS)/European Nuclear Society (ENS) international meeting on fifty years of controlled nuclear chain reaction: past, present, and future, Chicago, IL (United States), 15-20 Nov 1992; ISSN 0003-018X
Country of Publication:
United States
Language:
English