[KSCI] Korea Science Citation Index Service

Irradiation Assisted Stress Corrosion Cracking of Austenitic Stainless Steels in Water Reactors

Yonezawa, Toshio (Fracture and Reliability Research Institute, Tohoku University)

Publication Information

Corrosion Science and Technology / v.7, no.2, 2008 , pp. 77-84 More about this Journal

Abstract

Based upon the good compatibility to neutron irradiation and high temperature water environment, austenitic stainless steels are widely used for core internal structural materials of light water reactors. But, recently, intergranular cracking was detected in the stainless steels for the core applications in some commercial PWR plants. Authors studied on the root cause of the intergranular cracking and developed the countermeasure including the alternative materials for these core applications. The intergranular cracking in these core applications are defined as an irradiation assisted mechanical cracking and irradiation assisted stress corrosion cracking. In this paper, the root cause of the intergranular cracking and its countermeasure are summarized and discussed.

Keywords

irradiation assisted stress corrosion cracking; neutron irradiation; austenitic stainless steels; control rod; baffle former bolt; swelling;

Citations & Related Records

Reference

1	P. M. Scott, W. Foot, L. A. Goldsmith, S. Dumbill, T. M. Williams, J. M. Perks, C. A. English, and W. G. Burns, NEA/UNIPEDE Specialists Mtg. on Life-Limiting & Regulatory Aspects of Core Internals and Pressure Vessels, Stockholm (1987)
2	K. Fujimoto, T. Yonezawa, E. Wachi, Y. Yamaguchi, M. Nakano, R. P. Shogan, J. P. Massoud, and T. R. Mager, Proceedings of the 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors-, p.299 (2005)
3	T. Yonezawa, K. Arioka, H. Kanasaki, E. Otsuka, S. Urata, H. Mizuta, Proceedings of the International Conference on Fontevraud IV, p.237, (1998)
4	K. Fujimoto, T. Yonezawa, T. Iwamura, K. Ajiki, S. Urata, Corrosion Engineering, 49, 701 (2000)
5	T. Yonezawa, K. Fujimoto, H. Kanasaki, T. Iwamura, S. Nakada, K. Ajiki, S. Urata, Corrosion Engineering, 49, 655 (2000) DOI
6	J. Conermann, R. P. Shogan, K. Fujimoto, T. Yonezawa, Y. Yamaguchi, Proceedings of the Twelfth International Conference on "Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors", p.277, Salt Lake (2005)
7	T. Yonezawa, T. Iwamura, K. Fujimoto, K. Ajiki, Proceedings of the Ninth International Symposium on "Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors", p.1015, Newport Beach (1999)
8	T. Matsuoka, T. Yonezawa, K. Nakamura, K. Murakami, J. Shimizu, and T. Nagata, J. of Nuclear Science and Technology, 35, 564 (1998) DOI
9	C. Janssen, Unpublished Paper (2002)
10	A. J. Jacobs, Letter Report and Literature Search, GE Nuclear Energy, San Jose, (1979)
11	T. Yonezawa, K. Fujimoto, T. Iwamura, S. Nishida, ASTM STP 1401, 224 (2000)
12	J. E. Moon, H. W. Keller, D. J. Colburn, Proceedings of the International Conference on Fontevraud III, p.726 (1994)
13	P. L. Andresen, F. P. Ford, S. M. Murphy, and J. M. Perks, Proceedings of the 4th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor-, p.1, NACE, Jekyll Island (1990)
14	P. Scott; J. Nuclear Materials, 211, 101 (1994) DOI ScienceOn
15	M. Kodama, S. Nishimura, J. Morisawa, S. Suzuki, S. Shima, and M. Yamamoto, Proceedings of the 5th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors-, p.948, Monterey (1991)
16	M. P. Monahan, R. Kohli, J. Santucci, P. Sipush, R. L. Harris, Trans. of 9th SMiRTC, p.75 (1987)
17	R. Cauvin, O. Goltrant, Y. Rouillon, E. Verzaux, A. Cazus, P. Dubuisson, P. Poitrenaud, S. Bellet, Proceedings of the International Conference on Fontevraud III, p.54, (1994)
18	T. Yonezawa, K. Fujimoto, H. Kanasaki, T. Iwamura, S. Nakada, K. Ajiki, K. Sasaki, Proceedings of the International 8th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors-, p.823, (1997)