Effects of temperature on stress corrosion cracking behavior of stainless steel and outer oxide distribution in cracks due to exposure to high-temperature water containing hydrogen peroxide
Source abstract
Abstract
Abstract Cracking growth tests were conducted in high-temperature water containing hydrogen peroxide (H2O2) at 561–423 K to evaluate the effects of H2O2 on stress corrosion cracking (SCC) of stainless steel (SS) at temperature lower than the boiling water reactor (BWR) operating temperature. Small compact tension (CT) specimens were prepared from thermally sensitized type 304 SS. Despite the observation of only a small portion intergranular SCC (IGSCC) near the side groove of the CT specimen at 561 K in high-temperature water containing 100 ppb H2O2, the IGSCC area expanded to the central region of the CT specimens at 423 and 453 K. Effects of H2O2 on SCC appeared intensely at temperature lower than the BWR operating temperature because of a reduction in the thermal decomposition of H2O2. To estimate the environment in the cracks, outer oxide distribution on the fracture surface and the fatigue pre-crack were examined by laser Raman spectroscopy and thermal equilibrium calculation was performed.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Hydrogen embrittlement and corrosion behaviors in metals · High Temperature Alloys and Creep · Fatigue and fracture mechanics
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (20)
Show source-provided references
1. T. Okamura, A. Sakashita, T. Fukuda, H. Yamashita, T. Futami, in: Trans of the 17th Int. Conf. on Structural Mechanics in Reactor Technology, #WG01-1, 2003, p. 1.
2. Suzuki · E-J. Adv. Maint. · 2009 · 1 · 1
3. Y. Wada, K. Ishida, M. Tachibana, in: Proc. of the 11th Int. Conf. Environmental Degradation of Materials in Nuclear Systems, 2003, p. 488.
4. Uchida · J. Nucl. Sci. Technol. · 1998 · 35 · 30110.1080/18811248.1998.9733860 ↗
5. Kim · Corrosion · 1999 · 55 · 8110.5006/1.3283969 ↗
6. Uchida · J. Nucl. Sci. Technol. · 2005 · 41 · 6610.1080/18811248.2005.9726365 ↗
7. Murayama · J. Nucl. Sci. Technol. · 2002 · 39 · 119910.1080/18811248.2002.9715311 ↗
8. Lin · Int. J. Chem. Kinet. · 1991 · 23 · 97110.1002/kin.550231103 ↗
9. K. Hide, T. Onchi, M. Mayuzumi, S. Dumbill, in: Proc. 10th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, 2002.
10. ASTM E-399-90, “Standard Test Method for Plane-Strain Fracture Toughness of Metallic Materials”.
11. M. Kato, Nyumon/Ten-i-ron, Syoka-bou, Tokyo, 100–108, ISBN: 4-7853-6106-9, 2007 (in Japanese).
12. H. Sunada, Ensyu/Zairyo-shiken-nyumon, Taiga-syuppan, Tokyo, 73–74, ISBN: 4-88661-435-3, 1987 (in Japanese).
13. Ozawa · J. Nucl. Sci. Technol. · 1983 · 20 · 103910.1080/18811248.1983.9733505 ↗
14. A. Jenssen, C. Jansson, in: Proc. of the 10th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, 2002.
15. Wada · J. Nucl. Sci. Technol. · 2001 · 38 · 18310.1080/18811248.2001.9715020 ↗
16. Miyazawa · J. Nucl. Sci. Technol. · 2005 · 42 · 23310.1080/18811248.2005.9726384 ↗
17. Miyazawa · J. Nucl. Sci. Technol. · 2006 · 43 · 88410.1080/18811248.2006.9711173 ↗
18. Nakano · J. Nucl. Mater. · 2013 · 441 · 34810.1016/j.jnucmat.2013.05.073 ↗
19. Hirayama · Boshoku Gijutsu · 1985 · 34 · 86
20. 1993