Back to Search
Start Over
Oxidation of 304 stainless steel in high-temperature steam
- 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.
- Subjects :
- Cladding (metalworking)
Nuclear and High Energy Physics
Materials science
Metallurgy
Kinetics
Oxide
Polishing
Atmospheric temperature range
chemistry.chemical_compound
Reaction rate constant
Nuclear Energy and Engineering
chemistry
Residual stress
General Materials Science
Loss-of-coolant accident
Subjects
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