Correlation between IASCC growth behavior and plastic zone size of crack tip in 3.5 dpa neutron irradiated type 304L SS CT specimen

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

Volumn 1, Issue , 2007, Pages 286-299

  Nakamura, Tomomi ^a   Koshiishi, Masato ^a   Torimaru, Tadahiko ^b   Kitsunai, Yuji ^b   Takakura, Kenichi ^c   Nakata, Kiyotomo ^c   Ando, Masami ^c   Ishiyama, Yoshihide ^a,b   Jenssen, Anders ^d  

^a HITACHI GE NUCLEAR ENERGY LTD   (Japan)

^b NIPPON NUCLEAR FUEL DEVELOPMENT CO LTD   (Japan)

^c JAPAN NUCLEAR ENERGY SAFETY ORGANIZATION   (Japan)

^d STUDSVIK NUCLEAR AB   (Sweden)

Author keywords

[No Author keywords available]

Indexed keywords

ABS RESINS; CRACK TIPS; CRACKING (CHEMICAL); DEGRADATION; ELECTRIC INSTRUMENT TRANSFORMERS; ELECTRIC POWER SYSTEMS; ELECTRIC POWER TRANSMISSION NETWORKS; NUCLEAR ENERGY; POWER TRANSMISSION; STEEL TESTING;

ENVIRONMENTAL DEGRADATION; INTERNATIONAL CONFERENCES; NUCLEAR POWER SYSTEMS;

STAINLESS STEEL;

EID: 51649087757     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (8)

1. th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Salt Lake City, August 2005, 365-376
2. K. Chatani et al., "Crack Growth Rate of Low Carbon Austenitic Stainless Steels Irradiated in Simulated BWR Condition", Proceedings of 13th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, to be published August 2007.
3. Peter L. Andresen, "K / Size Effects on SCC in Irradiated, Cold Worked and Unirradiated Stainless Steel" Proc. Eleventh International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, ANS, 2003
4. A. Jenssen, P. Efsing, K. Gott and P-O. Andersson, "Crack Growth Behaviour of Irradiated Type 304L Stainless Steel in Simulated BWR Environment" Proc. Eleventh International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, ANS, 2003
5. S. M. Bruemmer et al., "Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals", Journal of Nuclear Materials, Vol.274, 1999 pp.299-314
6. K. Fukuya K. Fujii and Y. Kitsunai, "Deformation structure in 316 stainless steel irradiated in a PWR" Proc. 12th Int. Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -, TNS, p.389, 2005
7. H. Nishioka, K. Fukuya, K. Fujii and Y. Kitsunai, "Deformation structure in stainless steels irradiated in a PWR" INSS Journal, Vol. 13, p. 147, 2006
8. O. K. Chopra, E. E. Gruber and W. J. Shack, "Fracture Toughness and Crack Growth Rates of Irradiated Austenitic Stainless Steels", NUREG/CR-6826, August 2003.