Effects of hydrogen peroxide on intergranular stress corrosion cracking of stainless steel in high temperature water, (I)

Journal of Nuclear Science and Technology

Volumn 35, Issue 4, 1998, Pages 301-308

  Uchida, Shunsuke ^a   Shigenaka, Naoto ^a   Tachibana, Masahiko ^a   Wada, Yoichi ^a   Sakai, Masanori ^a   Akamine, Kazuhiko ^a   Ohsumi, Katsumi ^a  

^a HITACHI LTD   (Japan)

Author keywords

Boiling water reactors; Concentration dependence; Electrochemical cowusion potential; Hydrogen peroxide; Stainless steels; Stress cowusion cracking; Temperature range 0400 1,000 K; Water chemistry

Indexed keywords

AUTOCLAVES; COMPOSITION EFFECTS; COOLING SYSTEMS; CORROSION PROTECTION; ELECTROCHEMICAL CORROSION; HYDROGEN PEROXIDE; HYSTERESIS; OXIDATION; POLYTETRAFLUOROETHYLENES; STAINLESS STEEL; STEEL CORROSION; STRESS CORROSION CRACKING;

ELECTROCHEMICAL CORROSION PROTECTION;

BOILING WATER REACTORS;

EID: 0032050880     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.1080/18811248.1998.9733860     Document Type: Article

References (22)

1. Cowan, R. L.: The mitigation of IGSCC of BWR internals with hydrogen water chemistry, Proc. Int. Conf. Water Chemistry of Nuclear Reactor Systems, Water Chemistry J, Brit. Nucl. Energy Soc., 196, (1996).
2. Takiguchi, H., et al Differences in effectiveness of hydrogen water chemistry of boiling water reactors caused by reactor types, Submitted to J. Nucl. Sci. Technol. Uchida, S., et al: Nucl. Technol., 110, 250 (1995).
3. Fejes, P. P.: Deaeration practices in Swedish BWRs, Proc. Semin. Countermeasures for BWR Pipe Cracking, Palo Alto, CA., 1980, Elec. Power Res. Inst., (1980).
4. Row, R. J., et al: Suppression of radiolytic oxygen produced in a BWR by feedwater hydrogen addition, Water Chemistry 3, Brit. Nucl. Energy Soc., 23, (1984).
5. Cowan, R. L., et al: Experience with hydrogen water chemistry in boiling water reactors, Proc. Int. Conf. Water Chemistry of Nuclear Reactor Systems, Water Chemistry 4, Brit. Nucl. Energy Soc., 29, (1986).
6. Hydrogen water chemistry guidelines; 1987 Revision, EPRI NP-4947-SR, (1988).
7. Hydrogen water chemistry for BWRs: Materials behavior, EPRI NP-5080, (1987).
8. Cowan, R. L., et al: Hydrogen water chemistry in BWRs, Proc. 5th Int. Symp. Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, Monterey, CA., Natl. Assoc. Corrosion Eng., 50 (1991).
9. Kitabata, T.: Long term chemistry trends with hydrogen water chemistry in the Fugen Nuclear Power Station, Proc. 1991 JAIF Conf. On Water Chemistry in Nuclear Power Plants, Fukui, Japan, 107 (1991).
10. Ashida, S., et al: First experience of hydrogen water chemistry at a Japanese BWR, Water Chemistry of Nuclear Reactor Systems 6, Brit. Nucl. Energy Soc., 103(1992).
11. Sakai, M., et al: Corrosion potential monitoring and its simulation in BWR conditions, Proc. 12th Int. Corrosion Congress—Corrosion Control for Low Cost Reliability, 5B, 4060 (1992).
12. Ford, F. P., et al: EPRI NP-5064M Project 2006-6 Fincil Rep., (1987).
13. Kim, Y. J., et al: Development of ECP models for BWR application, Proc. 7th Int. Symp. Environmental Degradation of Materials in Nuclear Power Systems— Water Reactors, Breckenridge, CO., Natl. Assoc. Corrosion Eng., 699 (1995).
14. Lin, C. C., et al: Int. J. Chem. Kinetics, 23, 971 (1991).
15. Hiroishi, D.: Homogeneous and heterogeneous decomposition of hydrogen peroxide in high temperature water, Proc. Int. Conf. Water Chemistry of Nuclear Reactor Systems, Water Chemistry 5, Brit. Nucl. Energy Soc., 311, (1989).
16. Fujimori, H., et al: A procedure for evaluating residual life of major components in light water reactors, Proc. 7th Int. Symp. Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, Breckenridge, CO., 959 (1995).
17. Wada, Y., et al: Radiolytic environments around RPV internals of BWR, Proc. Int. Symp. Plant Aging and Life Prediction of Corrodible Structures, NACE, Sapporo, May, 15-18, (1995).
18. Wada, Y., et al: Numerical simulation of SCC environment in a BWR primary coolant system, Proc. 8th Int. Symp. Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Ameria Island, FA., 574 (1997).
19. Anzai, H., et al: Corrosion Sci., 36, 1201 (1994).
20. Ichikawa, N., et al: Estimation of corrosion potential of stainless steel in BWR primary circuit, Proc. Int. Conf. Water Chemistry of Nuclear Reactor Systems, Water Chemistry 6, Vol. 2, 127 (1992).
21. Indig, M. E., Nelson, J. L.: Corrosion, 47, 202 (1991).
22. Hishida, M., et al: Corrosion, 41, 570 (1985)