Unified interpretation of crack growth rates of Ni-base alloys in LWR environments

Journal of Pressure Vessel Technology, Transactions of the ASME

Volumn 128, Issue 3, 2006, Pages 318-327

  Lu, Zhanpeng ^a   Shoji, Tetsuo ^a  

^a TOHOKU UNIVERSITY   (Japan)

Author keywords

Alloy; Alloy 600; Boiling water reactor; Crack growth rate; Crack tip strain rate; Light water reactor; Nickel base; Pressurized water reactor; Stress corrosion cracking; Theoretical modeling

Indexed keywords

BOILING WATER REACTORS; COMPUTER SIMULATION; CRACK PROPAGATION; DEFORMATION; LIGHT WATER REACTORS; OXIDATION; PRESSURIZED WATER REACTORS; STRESS ANALYSIS; STRESS CORROSION CRACKING; WATER;

ALLOY 600; CRACK GROWTH RATE (CGR); CRACK TIP STRAIN RATE; THEORETICAL MODELING;

NICKEL ALLOYS;

EID: 33748518935     PISSN: 00949930     EISSN: None     Source Type: Journal    
DOI: 10.1115/1.2217964     Document Type: Article

References (26)

1. Scott, P. M., and Benhamou, C., 2001, "An Overview of recent Observations and Interpretations of IGSCC in Nickel Base alloys in PWR Primary Water," Proc. of the 10th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, NACE.
2. Scott, P. M., and Combrade, P., 2003, "On the Mechanism of Stress Corrosion Crack Initiation and Growth in Alloy 600 Exposed to PWR Primary Water," 11th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Skamania, ANS.
3. Hong, S. L., Boursier, J. M., Amzallag, C., and Daret, J., 2001, "Measurement of Stress Corrosion Growth Rates in Weld Alloy 182 in Primary Water," Proc. of the 10th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, NACE.
4. Bamford, W. H., Foster, J., Hsu, K. R., Tunon-Sanjur, L., and McIlree, A., 2001, "Alloy 182 Weld Crack Growth, and its Impact on Service-Induced Cracking in Operating PWR Plant Piping," Proc. of the 10th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE.
5. Shoji, T., Suzuki, S., and Ballinger, R. G., 1995, "Theoretical Prediction of SCC Growth Behavior," Proc. 7th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE, pp. 881-889.
6. Shoji, T., 2003, "Progress in the Mechanistic Understanding of BWR SCC and Its Implication to the Prediction of SCC Growth Behavior in Plants," 11th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, ANS, Skamania, pp. 588-598.
7. Shoji, T., Lu, Z. P., and Peng, Q. J., 2003, "Experimental and Numerical Approaches for Characterizing the Crack Growth Behavior of Alloy 600 in PWR Primary Water, and Life Time Predictions for Welded Structures," Proc. Conf. on Vessel Penetration Inspection, Crack Growth and Repair, Gaithersburg, MD, U.S. Nuclear Regulatory Commission, pp. 309-336.
8. Shoji, T., Li, G. F., Kwon, J. H., Matsushima, S., and Lu, Z. P., 2003, "Quantification of Yield Strength Effects on IGSCC of Austenitic Stainless Steels in High Temperature Waters," 11th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, ANS, Skamania, pp. 834-844.
9. Amzallag, C., and Vaillant, F., 1999, "Stress Corrosion Crack Propagation Rates in Reactor Vessel Head Penetrations in Alloy 600," Proceedings of the 9th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Newport Beach, CA: TMS, pp. 235-241.
10. Materials Reliability Program (MRP)-July, 2002, " Crack Growth Rates for Evaluating Primary Water Stress Corrosion Cracking (PWSCC) of Thick-wall Alloy 600 Material" (MRP-55), By PWR Materials Reliability Program Alloy 600 Issues Task Group.
11. Amzallag, C., Boursier, J. M., Pages, C., and Gimond, C., 2001, "Stress Corrosion Life Assessment of 182 and 82 Welds Used in PWR Components," Proc. of the 10th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE.
12. Magdowski, R., Vaillant, F., Amzallag, C., and Speidel, M. O., 1997, "Stress Corrosion Crack Growth Rates of Alloy 600 in Simulated PWR Coolant," Proc. of the 8th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, S. M. Bruemmer, ed., American Nuclear Society, La Grange Park, IL, pp. 333-338.
13. Amzallag, C., Hong, S. Le, Page, C., and Gelpi, A., 1999, "Stress corrosion life assessment of alloy 600 components," Proceedings of the 9th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Newport Beach, CA: TMS, pp. 243-250.
14. Foster, J. P., Bamford, W. H., Pathania, R. S., and McIlree, A., 2001, "Effects of Loading on Alloy 600 Crack Growth Rate Behavior," Proc. 10th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE.
15. Foster, J. P., Bamford, W. H., and Pathania, R. S., 2003, "Alloy 600 Crack Growth Rate Stress Intensity Dependence," 11th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Skamania, ANS. pp. 156-165.
16. Speidel, M. O., and Magdowski, R., 2000, "Stress Corrosion Crack Growth in Alloy 600 Exposed to PWR and BWR Environments," Corrosion/2000, NACE, TX, Paper No.222.
17. Moshier, W. C., and Brown, C. M., 2000, "Effects of Cold Work and Processing Orientation on Stress Corrosion Cracking Behavior of Alloy 600, " Corrosion (Houston), 56(3), pp. 307-320.
18. Cassagne, T., Caron, D., Daret, J., and Lefevre, Y., 1999, "Stress Corrosion Crack Growth Measurements in Alloys 600 and 182," Proceedings of the 9th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Newport Beach, CA: TMS, pp. 217-224.
19. Amzallag, C., Boursier, J. M., Pages, C., and Gimond, C., 2002, "Stress Corrosion Life Experience of 182 and 82 Welds in French PWR's," Fontevraud V, Fontevraud, French Nuclear Energy Society, Paper No. 026, CDROM.
20. Ford, F. P., 1996, "Quantitative Prediction of Environmentally Assisted Cracking," Corrosion (Houston), 52(5), pp. 375-395.
21. Birks, N., and Meier, G. H., 1983, Introduction to High Temperature Oxidation of Metals, Edward Arnold Ltd, London, p. 42.
22. Badini, C., and Laurella, F., 2001, "Oxidation of FeCrAl alloy: Influence of Temperature and Atmosphere on Scale Growth Rate and Mechanism," Surf. Coat. Technol., 135, pp. 291-298.
23. Heusler, K. E., 1997, "Fundamental Aspects of the Corrosion of Alloys," Corros. Sci., 39(7), pp. 1177-1191.
24. Gao, Y. C., and Kwang, K. C., 1981, "Elastic-Plastic Fields in Steady Crack Growth in a Strain-Hardening Material," 5th International Conference on Fracture, France, 2, pp. 669-682.
25. Gerberich, W. W., Davidson, D. L., and Kaczorowski, M., 1990, "Experimental and Theoretical Strain Distributions for Stationary and Growing Cracks," J. Mech. Phys. Solids, 38(1), pp. 87-113.
26. Champigny, F., Chapelier, F., Amzallag, C., and Vaillant, F., 2003, "Maintenance Strategy of Inconel Components in PWR Primary System in France," Proc. Conf. on Vessel Penetration Inspection, Crack Growth and Repair. Gaithersburg, MD, U.S. Nuclear Regulatory Commission, pp. 85-94.