The effect of hold time on the crack growth rate of sensitized 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 157-166

  Jenssen, Anders ^a   Jansson, Christer ^b   Sundberg, Johan ^a  

^a STUDSVIK NUCLEAR AB   (Sweden)

^b SwedPower AB   (Sweden)

Author keywords

BWR; Crack Growth Rate; Hold Time; Partial Periodic Unloading; Type 304 SS

Indexed keywords

BOILING WATER REACTORS; CRACK PROPAGATION; FATIGUE TESTING; GRANULAR MATERIALS; HARDENING; LIGAMENTS;

CRACK GROWTH RATE; HIGH TEMPERATURE WATER; HOLD TIME; PARTIAL PERIODIC UNLOADING;

STAINLESS STEEL;

EID: 33745210779     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (10)

1. A. Jenssen, M. König, "Influence of Environmental and Mechanical Factors on the Crack Growth Rate of Austenitic Materials under Simulated BWR Conditions" (Presented at Symposium on Water Chemistry and Corrosion in Nuclear Power Plants in Asia 2003, Fukuoka, Japan, Nov. 11-12, 2003).
2. th Int'l Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, TMS, Warrandale, PA, 1999, 411).
3. th Int'l Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, TMS, Warrandale, PA, 1999, 279).
4. th Int'l Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, TMS, Warrandale, PA, 1993, 373).
5. th Int'l Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, ANS, La Grange Park, IL, 1997, 667).
6. rd Int'l Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, TMS, Warrandale, PA, 1998).
7. th Int'l Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, TMS, Warrandale, PA, 1999, 361-370).
8. C. Jansson, U. Morin, "Material data book - Phase 2 (MD-02) Fatigue Crack Growth in Reactor Materials (in Swedish)" (Report GEK 87/95, Vattenfall Energisystem, Sweden, 1995).
9. C. Jansson, "Material data book MD-01 revision 3 - Stress Corrosion Crack Growth in Reactor Materials (in Swedish)" (Report T-SEK 41/99, SwedPower AB, Sweden, 1999).
10. A. Jenssen, P. Efsing, J. Sundberg, "Influence of Heat Treatment, Aging and Neutron Irradiation on the Fracture Toughness and Crack Growth Rate in BWR Environments of Alloy X-750" (Paper presented at this conference).