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Title: Corrosion studies for the sodium cooled fast breeder reactor program

Conference ·
OSTI ID:4113194

Materials presently identified for the Liquid Metal Cooled Fast Breeder Reactor (LMFBR) are primarily iron-base alloys such as Types 304 and 316 stainless steels or the ferritic 2$sup 1$$/$$sub 4$Cr--1Mo alloy. Nickel base materials, such as Inconel 718, are also used to some extent for specialized applications requiring high strength and moderately good thermal fatigue resistance. Although the iron and nickel base materials are relatively inert to the sodium coolant under normal operating conditions, sufficient corrosive processes occur to warrant design compensations, and hence minimize material problems encountered over the 25-30 year design life of the reactor plant. Considerations of wall thinning rates, particularly for thin walled structures such as fuel cladding or heat transfer tubing, changes in interstitial element contents for iron base alloys, changes in surface composition or microstructure which could lead to high wear rates or friction coefficients between contacting interfaces, and deposition of corrosion products in cold leg regions of the sodium system with resulting effects on radioactive maintenance, flow blockage, and heat transfer are described. 16 references. (auth)

Research Organization:
Westinghouse Electric Co., Madison, PA
NSA Number:
NSA-33-014021
OSTI ID:
4113194
Resource Relation:
Conference: Proceedings of the symposium on corrosion problems in energy conversion and generation, New York, New York, USA, 15 Oct 1974; Other Information: See CONF-7410138--. Orig. Receipt Date: 30-JUN-76; Related Information: Corrosion problems in energy conversion and generation
Country of Publication:
United States
Language:
English