Development of new ferritic cladding materials for metal-fueled FBRs
- Central Research Institute of the Electric Power Industry, Tokyo (Japan)
- 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
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Related Subjects
36 MATERIALS SCIENCE
FBR TYPE REACTORS
FUEL CANS
FERRITIC STEELS
SWELLING
ALLOY NUCLEAR FUELS
CREEP
LIQUID METAL FUELS
LMFBR TYPE REACTORS
MECHANICAL PROPERTIES
RESEARCH PROGRAMS
TESTING
ALLOYS
BREEDER REACTORS
ENERGY SOURCES
EPITHERMAL REACTORS
FAST REACTORS
FUELS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID FUELS
LIQUID METAL COOLED REACTORS
MATERIALS
NUCLEAR FUELS
REACTOR MATERIALS
REACTORS
SOLID FUELS
STEELS
210500* - Power Reactors
Breeding
360103 - Metals & Alloys- Mechanical Properties