Evaluation of IGSCC growth behavior of 316NG PLR piping in BWR

American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP

Volumn 479, Issue , 2004, Pages 217-223

  Kumagai, Katsuhiko ^a   Suzuki, Shunichi ^a   Mizutani, Jun ^a   Shitara, Chikashi ^a   Yonekura, Kazuyoshi ^b   Masuda, Minoru ^c   Futami, Tsuneo ^d  

^a TOKYO ELECTRIC POWER COMPANY   (Japan)

^b TOSHIBA CORPORATION   (Japan)

^c HITACHI LTD   (Japan)

^d CENTRAL RESEARCH INSTITUTE OF ELECTRIC POWER INDUSTRY   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

FUSION BOUNDARY; HARDENED MATERIALS; INTER GRANULAR STRESS CORROSION CRACKING (IGSCC); WELD JOINTS;

CRACK PROPAGATION; DATA ACQUISITION; GROWTH (MATERIALS); PIPING SYSTEMS; STAINLESS STEEL; STRAIN RATE; STRESS CORROSION CRACKING;

BOILING WATER REACTORS;

EID: 7744228580     PISSN: 0277027X     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1115/PVP2004-2666     Document Type: Conference Paper

References (8)

1. Andresen, P. L., et al., 2002, "Stress Corrosion Crack Growth Rate Behavior of Various Grades of Cold Worked Stainless Steel in High Temperature Water", Corrosion, Paper 02511, NACE, Houston, TX.
2. Andresen, P. L., et al., 2003, "Effects of Yield Strength, Corrosion Potential, Stress Intensity Factor, Silicon and Grain Boundary Character on the SCC of Stainless Steels", Proc. 11th international symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, pp.816-833.
3. Ehrnsten, Ulla, 2002, "Intergranular Cracking of AISB16NG Stainless Steel in BWR Environment", Proc. 10th international symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors.
4. Japan Society of Mechanical Engineering, 2002, "Codes for Nuclear Power Generation Facilities - Rules on Fitness-for-Service for Nuclear Power Plants-" JSME S NA1.
5. Jenssen, A., et al., 1995, "Crack propagation in Stainless steels and Nickel Base Alloys in a Commercial Operating", Proc. 7th international symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, pp.553-562.
6. Jones, Russsell H., et al., 1999, "Stress-Corrosion Cracking Materials Performance and Evaluation", ASM International
7. Okamura, Y., et al., 2003, "The latest issues of Core Shroud and Recirculation Piping in Japanese BWRs", Trans. of SMiRT 17.
8. Suzuki, S., et al., 2004, "Study on the SCC Growth of Alloy 182 under Constant Displacement Condition in High Temperature Oxygenated Water", Proc. ASME/JSME PVP2004.