Corrosion fatigue behavior of cold-worked 304L stainless steel in a simulated BWR coolant environment
Description
Fatigue crack growth tests were performed to evaluate the effect of cold work on the fatigue behavior of 304L stainless steel in the ambient air at room temperature and 300degC and in a simulated BWR coolant environment, respectively. The fatigue crack growth rates (FCGRs) for the as-received (AR) and cold-rolled specimens as room temperature were in the same range and the FCGRs obtained at 300degC in air were higher than at room temperature. In addition, the FCGRs for the AR specimens were higher at 300degC in air compared with those for the cold-rolled. The specimens tested in the water environment at 300degC showed higher corrosion fatigue crack growth rates (CFCGRs) relative to those measured in air at room temperature and 300degC. Local quasi-cleavages could account for the observation that the FCGRs in air at 300degC were faster than at room temperature. The dominant fracture features of quasi-cleavages, along with corrosion products, were observed with all the 304L specimens tested in the simulated BWR water environment, which could be related to the higher crack growth rates in the corrosive environment. (author)
Additional details
Publishing Information
- Journal Title
- Materials Transactions
- Journal Volume
- 50
- Journal Issue
- 3
- Journal Page Range
- p. 657-663
- ISSN
- 1345-9678
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 40090646
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; COOLANTS; CORROSION FATIGUE; CORROSION PRODUCTS; CRACK PROPAGATION; ENVIRONMENT; FRACTURES; MARTENSITE; ROLLING; SIMULATION; STAINLESS STEEL-304L; TEMPERATURE RANGE 0273-0400 K; TEMPERATURE RANGE 0400-1000 K; WATER CHEMISTRY
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHEMISTRY; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CORROSION RESISTANT ALLOYS; ENRICHED URANIUM REACTORS; FABRICATION; FAILURES; FATIGUE; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; LOW CARBON-HIGH ALLOY STEELS; MATERIALS; MATERIALS WORKING; MECHANICAL PROPERTIES; NICKEL ALLOYS; POWER REACTORS; REACTORS; STAINLESS STEELS; STEEL-CR19NI10-L; STEELS; TEMPERATURE RANGE; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 30 refs., 9 figs., 2 tabs.