Carbon transfer behavior of materials for liquid-metal fast breeder reactor steam generators

Journal Article · Mon Mar 01 04:00:00 EST 1976 · Nucl. Technol., v. 28, no. 3, pp. 452-470

OSTI ID:4091898

Matsumoto, K; Ohta, Y; Kataoka, T

To examine the compatibility with liquid sodium possessed by structural materials for LMFBR steam generators, tests were conducted on selected steels in a sodium loop facility. The materials tested were ferrite 2$sup 1$$/$$sub 4$ Cr--1 Mo, 2$sup 1$$/$$sub 4$ Cr--1 Mo--1 Nb, high Cr--1 Mo, and austenitic AISI Type 316 stainless steels. A method is proposed for estimating the rate of decarburization of the specimen by integrating the distribution curves of the carbon content determined from emission spectroscopic analysis of layers underlying the surface, which are successively uncovered by precision grinding. The decarburization behavior was found to reflect differences in the heat treatment history of the specimen, carbon loss being found to be more rapid on annealed than on normalized and tempered steels. (auth)

• Research Organization: Ishikawajima-Harima Heavy Industries Co., Ltd., Yokohama City, Japan
• NSA Number: NSA-33-028045
• OSTI ID: 4091898
• Journal Information: Nucl. Technol., v. 28, no. 3, pp. 452-470, Journal Name: Nucl. Technol., v. 28, no. 3, pp. 452-470; ISSN NUTYB
• Country of Publication: United States
• Language: English

Related Subjects

*CHROMIUM-MOLYBDENUM STEELS-- DECARBURIZATION
*LMFBR TYPE REACTORS-- STEAM GENERATORS
*SODIUM-- CORROSIVE EFFECTS
*STEAM GENERATORS-- MATERIALS
210500* --Nuclear Power Plants--Power Reactors
Breeding
CARBON
COMPATIBILITY
LOSSES
N50210 -- Metals
Ceramics
& Other Materials--Metals & Alloys--Corrosion & Erosion & Surface Phenomena
N77500* --Reactors--Power Reactors
Breeding
NIOBIUM ALLOYS
STAINLESS STEEL-316
TEMPERATURE DEPENDENCE