Development of an in-core stress corrosion cracking test method and preliminary test results
- Central Research Inst. of Electric Power Industry, Komae City, Tokyo (Japan)
- Organization for Economic Cooperation and Development, Halden (Norway). Halden Reactor Project
An in-core stress corrosion cracking (SCC) test method was developed using internally gas-pressurized tubular specimens and extensometers to detect specimen failure. Specimens of this type can simulate a constant load or a dynamic load during irradiation in the reactor. Results showed the method successfully detected specimen failure during irradiation. Effects of normal water chemistry (NWC) and hydrogen water chemistry (HWC) on intergranular stress corrosion cracking (IGSCC) of thermally sensitized type 304 stainless steel ([SS] UNS S30400) were examined in a simulated boiling-water reactor (BWR) core environment. HWC was found effective in mitigating initiation of IGSCC during steady-state operation and during the temperature transient for thermally sensitized type 304 SS in a reactor core water environment.
- Sponsoring Organization:
- USDOE
- OSTI ID:
- 315926
- Journal Information:
- Corrosion, Journal Name: Corrosion Journal Issue: 2 Vol. 55; ISSN 0010-9312; ISSN CORRAK
- Country of Publication:
- United States
- Language:
- English
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