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Oxidation of 304 stainless steel in high-temperature steam

Authors :
Sinnosuke Yaguchi
Yasuo Harayama
Toshihisa Ishida
Source :
Journal of Nuclear Materials. 140:74-84
Publication Year :
1986
Publisher :
Elsevier BV, 1986.

Abstract

An experiment on oxidation of 304 stainless steel was performed in steam between 900°C and 1350°C, using the spare cladding of the reactor of the nuclear-powered ship Mutsu. The temperature range was appropriate for a postulated loss of coolant accident (LOCA) analysis of a LWR. The oxidation kinetics were found to obey the parabolic law during the first period of 8 min. After the first period, the parabolic reaction rate constant decreased in the case of heating temperatures between 1100°C and 1250°C. At 1250°C, especially, a marked decrease was observed in the oxide scale-forming kinetics when the surface treated initially by mechanical polishing and given a residual stress. This enhanced oxidation resistance was attributed to the presence of a chromium-enriched layer which was detected by use of an X-ray microanalyzer. The oxidation kinetics equation obtained for the first 8 min is applicable to the model calculation of a hypothetical LOCA in a LWR, employing 304 stainless steel cladding.

Details

ISSN :
00223115
Volume :
140
Database :
OpenAIRE
Journal :
Journal of Nuclear Materials
Accession number :
edsair.doi...........52aada81c5140c81f4d0bbca67a6eb10
Full Text :
https://doi.org/10.1016/0022-3115(86)90198-4