Stress intensity and temperature dependence for crack growth rate in weld metal Alloy 182 in primary PWR environment

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

Volumn , Issue , 2005, Pages 533-541

  Norring, Kjell ^a   Konig, Martin ^a   Lagerstrom, Jan ^b  

^a STUDSVIK NUCLEAR AB   (Sweden)

^b RINGHALS AB   (Sweden)

Author keywords

[No Author keywords available]

Indexed keywords

ACTIVATION ENERGY; CRACK PROPAGATION; PRESSURIZED WATER REACTORS; SERVICE LIFE; STRESS CORROSION CRACKING; STRESS INTENSITY FACTORS; WELDS;

ALLOY 182; CRACK GROWTH RATE; NICKEL-BASE WELD METAL; PRIMARY PWR ENVIRONMENT; SAFETY ANALYSIS;

NICKEL ALLOYS;

EID: 33745183122     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (7)

1. A. Jenssen et al "Assessment of Cracking in Dissimilar Metal Welds." (Paper presented at 10th Internat Symp on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors. Lake Tahoe, Nevada USA, Aug 2001).
2. A. Jenssen et al. "Structural Assessment of Defected Nozzle to Safe-End Welds in Ringhals 3 and 4." (Paper presented at Internat Symp Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors. Fontevraud 5, France, Sept 2002), 43 - 54.
3. G. A. White, J.Hickling, L. K.Mathews. "Crack growth rates for evaluating PWSCC of thick-wall Alloy 600 material." (Paper presented at the 11th Internat Symp on Environemental Degradation of Materials in Nuclear Power Systems-Water Reactors. Stevenson, WA, USA, Aug, 2003).
4. A. Jenssen, P. Efsing, C. Jansson and K. Norring. "A Swedish Perspective on PWSCC of Alloy 182" (Paper presented at EPRI 2005 PWSCC of Alloy 600 International Conference. Santa Ana Pueblo, USA March 2005).
5. S. Le Hong, J. M. Boursier, C. Amzallag, and J. Daret. "Measurements of stress Corrosion cracking growth rates in weld Alloy 182 in primary water of PWR" (Paper presented at 10th Internat Symp on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors. Lake Tahoe, Nevada USA, Aug 2001)
6. G. White, J. Hickling, and C. Harrington "MRP Developmnet of Crack Growth Rate Disposition Curves for Primary Water Stress Corrosion Cracking (PWSCC) of Thick-section Alloy 600 Components and Alloy 82, 182, and 132 Weldments." (Paper presented at EPRI 2005 PWSCC of Alloy 600 International Conference. Santa Ana Pueblo, USA March 2005)
7. R. Lindstrom, P. Lidar and J. Lagerstrom. "Crack growth of Alloy 182 in a simulated primary side PWR environment." (Paper presented at the 8th Internat Symp on Environemental Degradation of Materials in Nuclear Power Systems-Water Reactors. Amelia Island, GA, USA, Aug, 1997).