Development of an in-core stress corrosion cracking test method and preliminary test results

被引：4
作者：
Mayuzumi, M
Hide, K
Onchi, T
Karlsen, TM
Vitanza, C
机构：
[1] Cent Res Inst Elect Power Ind, Komae, Tokyo 2018511, Japan
[2] Org Econ Cooperat & Dev, Halden Reactor Project, N-1751 Halden, Norway
来源：
CORROSION | 1999年 / 55卷 / 02期
关键词：
high-temperature water; in-core testing; irradiation; nuclear environments; sensitization; stress corrosion cracking; type 304 stainless steel; welds;
D O I：
10.5006/1.3283977
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
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.
引用
收藏
页码：166 / 172
页数：7
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