Optimized chemical composition and heat treatment conditions of 316 CW and high-chromium austenitic stainless steels for PWR baffle former bolts

Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -

Volumn , Issue , 1999, Pages 1015-1026

  Yonezawa, T ^a   Iwamura, T ^a   Fujimoto, K ^a   Ajiki, K ^a  

^a MITSUBISHI HEAVY INDUSTRIES LTD   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

AGE HARDENING; AUSTENITE; CHROMIUM; COLD WORKING; COMPOSITION; GRAIN BOUNDARIES; NICKEL; PRESSURIZED WATER REACTORS; STRESS CORROSION CRACKING; THERMAL EXPANSION;

AUSTENITIC STAINLESS STEEL; HIGH CHROMIUM STEEL; IRRADIATION ASSISTED STRESS CORROSION CRACKING;

STAINLESS STEEL;

EID: 0033489292     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1002/9781118787618.ch106     Document Type: Conference Paper

References (11)

1. O. Wacher, et al.: Proceedings of the 8th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Myrtle Beach, (1997), p.812.
2. 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 Reactors-, Jekyll Island, Georgia, (1989), p.1.
3. P. Scott, et al.: NEA / UNIPEDE Specialists Mtg on Life Limiting & Regulatory Aspects of Core Internals and Pressure Vessels, Stockholm, (1987).
4. A. J. Jacobs: Letter Report and Literature Search, GE Nuclear Energy, San Jose, CA, (1979).
5. 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-, Monterey, California, (1991), p.948.
6. I. Suzuki, K. Fukuya, H. Kanasaki, M. Akiyama, Y. Mishima and T. R. Mager: International Conference on Nuclear Engineering Vol. 5 ASME (1996), p.205.
7. R. Cauvin, O. Golyrant, et al.: Fontevraud III, Vol. 1, 12-16 (1994), p.54.
8. T. Yonezawa, K. Fujimoto, H. Kanasaki, T. Iwamura, S. Nakada, K. Ajiki, K. Sakai: Proceedings of the 8th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors-, Amelia Island, (1997), p.823.
9. T. Yonezawa, K. Arioka, H. Kanasaki, K. Fujimoto, E. Otsuka, S. Urata, H. Mizuta: Fontevraud IV, Vol 1 (1998), p.237.
10. M. Kowaka, D. Kobayashi, T. Kudo: Sumitomo Kinzoku, Vol. 30 (1978), p.93.
11. T. Yonezawa, K. Onimura, N. Sakamoto, N. Sasaguri, H. Susukida: Proceedings of the International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors-, Myrtle Beach, (1997), p.345.