Improvement of IASCC Resistance for Austenitic Stainless Steels in PWR Environment

ASTM Special Technical Publication

Volumn , Issue 1401, 2001, Pages 224-238

  Yonezawa, Toshio ^a   Fujimoto, Koji ^a   Iwamura, Toshihiko ^a   Nishida, Seishi ^a  

^a MITSUBISHI HEAVY INDUSTRIES LTD   (Japan)

Author keywords

Aging; Coherency; Cold working; Irradiation assisted stress corrosion cracking; Irradiation induced segregation; PWR; Slow strain rate tensile test; Stainless steel

Indexed keywords

EID: 1942446195     PISSN: 00660558     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Article

References (13)

1. Wacher, O., Bruns, J., Wesseling, U., Kilian, R., and Roth, A., "Crack Initiation in the Nb-stabilized Austenitic Stainless Steel (A347) in the Core Shroud and Top Core Guide of a German Boiling Water Reactor - Description of the Extent of the Damage and Explanation of its Causes, "Proceedings of the 8th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Myrtle Beach, SC, American Nuclear Society, 1997, pp. 812-822.
2. Andresen, P. L., Ford, F. P., Murphy, S. M., and Perks, J. M., "State of Knowledge of Radiation Effects on Environmental Cracking in Light Water Reactor Core Materials," Proceedings of the 4th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors-, Jekyll Island, Georgia, American Nuclear Society, 1989, pp. 1-83-120.
3. P. Scott et al., NEA / UNIPEDE Specialists Mtg. on Life Limiting & Regulatory Aspects of Core Internals and Pressure Vessels, Stockholm, 1987.
4. Jacobs, A. J., Letter Report and Literature Search, GE Nuclear Energy, San Jose, CA, 1979.
5. Kodama, M., Nishimura, S., Morisawa, J., Suzuki, S., Shima, S., and Yamamoto, M., "Effect of Fluence and Dissolved Oxygen on IASCC in Austenitic Stainless Steels," Proceedings of the 5th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors-, Monterey, California, American Nuclear Society, 1991, pp. 948-959.
6. Suzuki, I., Fukuya, K., Kanasaki, H., Akiyama, M., Mishima, Y. and Mager, T. R., "Stress Corrosion Cracking of Irradiated Stainless Steels in Simulated PWR Primary Water" International Conference on Nuclear Engineering Vol. 5 ASME, 1996, pp. 205-213.
7. Cauvin, R., Golyrant, O., Rouillon, Y., Verzaux, E., Cazus, A., Dubuisson, P., Poitrenaud, P., and Bellet S., "Endommagement des Structures Internes Inferieures Soumises a Forte Fluence: Apports de L'Expertise," Proceedings of the International Symposium on FONTEVRAUD III, French Nuclear Energy Society, Vol. 1, 12-16, 1994, pp. 54-65.
8. Yonezawa, T., Fujimoto, K., Kanasaki, H., Iwamura, T., Nakada, S. Nakada, Ajiki, K., Sakai, K., "SCC Susceptibility of Irradiated Austenitic Stainless Steels for PWR," Proceedings of the 8th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors-, Amelia Island, American Nuclear Society, 1997, pp. 823-830.
9. Yonezawa, T., Arioka, K., Kanasaki, H., Fujimoto, K., Otsuka, E., Urata, S., and Mizuta, H., "IASCC Susceptibility and It's Improvement of Austenitic Stainless Steels for Core Internals of PWR," Proceedings of the International Symposium on FONTEVRAUD III, French Nuclear Energy Society, Vol. 1, 1998, pp. 237-248.
10. Kowaka, M., Kobayashi, D., and Kudo, T., Sumitomo Kinzoku, Vol. 30, 1978, p.93.
11. Yonezawa, T., Onimura, K., Sakamoto, N., Sasaguri, N., and Susukida, H., "Effect of Heat Treatment Conditions on Stress Corrosion Cracking Resistance of Alloy X-750 in High Temperature Water," J. Japan Inst. Metals, Vol. 48, No. 3, 1984, pp. 283-247.
12. Yonezawa, T., Yamaguchi, Y., and Iijima, Y., "Electron Micro Autoradiographic Observation of Tritium Distribution on Alloy X750," Proceedings of the 6th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors-, San Diego, California, August, American Nuclear Society, 1993, pp. 799-804.
13. Yonezawa, T., Onimura, K., Sakamoto, N., Sasaguri, N., Nakata, H., and Susukida, H. "Effect of Heat Treatment on Stress Corrosion Cracking resistance of High Nickel Alloys in High Temperature Water," Proceedings of the International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors-, Myrtle Beach, American Nuclear Society, 1987, pp. 345-366.