Stress corrosion crack growth behavior of cold worked austenitic stainless steel in high temperature water

Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors

Volumn , Issue , 2005, Pages 109-115

  Tsubota, M ^a   Katayama, Y ^a   Saito, Y ^a  

^a TOSHIBA CORPORATION   (Japan)

Author keywords

BWR; Crack Growth Rate; Hardness; Stainless Steel; Stress Corrosion Cracking

Indexed keywords

AUSTENITE; BOILING WATER REACTORS; COLD WORKING; CRACK PROPAGATION; HARDNESS; STAINLESS STEEL; STRESS CONCENTRATION; VICKERS HARDNESS TESTING;

COLD WORKED MATERIALS; CRACK GROWTH RATE; HARDNESS SCC SUSCEPTIBILITY (HVC); PLASTIC ZONE SIZE;

STRESS CORROSION CRACKING;

EID: 33745198669     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (5)

1. M.Tsubota, Y.Kanazawa, H.Inoue; Proceedings of the 7th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, p.519, 1995.
2. Y.Kanazawa, M.Tsubota, "CORROSION 94 ", Paper No. 237, NACE, Baltimore, Md, 1994.
3. ASTM Standard E1823, ASTM Annual Report, vol.3, 1997.
4. M.Tsubota, Y.Kanazawa, "CORROSION 94 ", Paper No. 238, NACE, Baltimore, Md, 1994.
5. D.Broak, "Elementary Engineering Fracture Mechanics", Martinus Nijihoff Publishers, 1982.