IASCC crack growth rate of neutron irradiated low carbon austenitic stainless steels in simulated BWR condition

Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007

Volumn 2, Issue , 2007, Pages 1082-1090

  Chatani, Kazuhiro ^a   Takakura, Kenichi ^b   Ando, Masami ^b   Nakata, Kiyotomo ^b   Tanaka, Shigeaki ^c   Ishiyama, Yoshihide ^d,e   Hishida, Mamoru ^e,f   Kaji, Yoshiyuki ^g  

^a NIPPON NUCLEAR FUEL DEVELOPMENT CO LTD   (Japan)

^b JAPAN NUCLEAR ENERGY SAFETY ORGANIZATION   (Japan)

^c TOSHIBA CORPORATION   (Japan)

^d HITACHI LTD   (Japan)

^e NFD ^*

^f INSTITUTE OF RESEARCH AND INNOVATION   (Japan)

^g JAPAN ATOMIC ENERGY AGENCY   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

AUSTENITIC STAINLESS STEEL; AUSTENITIC STEEL; BOILING WATER REACTORS; CRACK PROPAGATION; CRACKING (CHEMICAL); DEGRADATION; ELECTRIC POWER SYSTEMS; ELECTRIC POWER TRANSMISSION NETWORKS; METALS; NEUTRONS; NUCLEAR ENERGY; POWER TRANSMISSION; STAINLESS STEEL; SULFATE MINERALS;

AUSTENITIC; BASE METALS; COMPACT TENSION SPECIMENS; CORE REGIONS; CRACK-GROWTH RATES; INTERNATIONAL CONFERENCES; LOW CARBON; MATERIAL TESTING REACTOR; NUCLEAR POWER SYSTEMS; NUCLEAR SOCIETY; STAINLESS STEELS; WATER ENVIRONMENTS;

TESTING;

EID: 51849129208     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (11)

1. W. L. Clarke and A. J. Jacobs, "Effect of Radiation Environment on SCC of Austenitic Materials", Proceedings of First International Symposium on Environmental Degradation of Materials in Nuclear Power System-Water Reactors, Myrtle Beach, South Carolina, August 1983, 451-461.
2. F. Garzarolli et al., "Deformability of Austenitic Stainless Steels and Ni-base Alloys in the Core of a Boiling and a Pressurized Water Reactor", Proceedings of Third International Symposium on Environmental Degradation of Materials in Nuclear Power System-Water Reactors, Traverse City, Michigan, September 1987, 657-664.
3. A. J. Jacobs et al., "Radiation Effects on the Stress Corrosion and Other Selected Properties of Type-304 and Type-316 Stainless Steels", ibid., September 1987, 673-680.
4. A. J. Jacobs and G. P. Wozadlo, "Irradiation-Assisted Stress Corrosion Cracking a Factor in Nuclear Power Plant Aging", Proceedings of International Conference on Nuclear Power Plant Aging Availability Factors and Reliability Analysis, ASM, (1985), 173-182.
5. D. I. R. Norris, C. Baker, and J. M. Titchmarsh, "Compositional Profiles at Grain Boundaries in 20%Cr/25%Ni/Nb Stainless Steel", Proceedings of Symposium on Radiation-Induced Segregation of Stainless Steel held at Berkeley Nuclear Laboratory, CEGB, September 1986, 86-98.
6. H. Hanninen and Aho-Mantina, "Environment-Sensitive Cracking of Reactor Internals", Proceedings of Third International Symposium on Environmental Degradation of Materials in Nuclear Power System-Water Reactors, Traverse City, Michigan, September 1987, 77-92.
7. P. L. Andersen et al., "State of Knowledge of Radiation Effects on Environmental Cracking in Light Water Reactor Core Materials", Proceedings of Fourth International Symposium on Environmental Degradation of Materials in Nuclear Power System-Water Reactors, Jekyll Island, Georgia, August 1989, 83-121.
8. M. Kodama et al., "Effects of Fluence and Dissolved Oxygen on IASCC in Austenitic Stainless Steels", Proceedings of Fifth International Symposium on Environmental Degradation of Materials in Nuclear Power System-Water Reactors, Monterey, California, August 1991, 948-954.
9. K. Asano et al., "Changes in Grain Boundary Composition Induced by Neutron Irradiation on Austenitic Stainless Steels", Proceedings of Fifth International Symposium on Environmental Degradation of Materials in Nuclear Power System-Water Reactors, Monterey, California, August 1991, 838-842.
10. R. Sumiya et al., "K Validity Criterion of Neutron Irradiated Type 316L Stainless steel CT specimen for SCC growth test", Proceedings of 13th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, August 2007, to be published.
11. L. E. Thomas and Bruemmer, S. M., "Insights into Environmental Degradation Mechanisms from Analytical Transmission Electron Microscopy of SCC Cracks", Proceedings of Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 1999, p. 41.