Corrosion studies for the sodium cooled fast breeder reactor program

Conference · Tue Jan 01 04:00:00 EST 1974

OSTI ID:4113194

Schrock, S L; Whitlow, G A; Tedman, Jr, C S ^[1]

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1. ed.

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
• Country of Publication: United States
• Language: English

Related Subjects

*CHROMIUM-MOLYBDENUM STEELS-- CORROSION
*LMFBR TYPE REACTORS-- REACTOR MATERIALS
*NICKEL BASE ALLOYS-- CORROSION
*REACTOR MATERIALS-- CORROSION
*STAINLESS STEEL-304-- CORROSION
*STAINLESS STEEL-316-- CORROSION
210500* --Nuclear Power Plants--Power Reactors
Breeding
N50210 -- Metals
Ceramics
& Other Materials--Metals & Alloys--Corrosion & Erosion & Surface Phenomena
N77500* --Reactors--Power Reactors
Breeding
PERFORMANCE
SODIUM