Experience and assessment of stress corrosion cracking in L-grade stainless steel BWR internals

Nuclear Engineering and Design

Volumn 174, Issue 3, 1997, Pages 313-325

  Horn, R M ^a   Gordon, G M ^a   Ford, F P ^b   Cowan, R L ^a  

^a GE ENERGY   (United States)

^b GE GLOBAL RESEARCH   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

EID: 0000801486     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/s0029-5493(97)00131-3     Document Type: Article

References (32)

1. Alexander, J.E. et al., 1982. Alternate alloys for BWR piping applications. EPRI, NP-2671-LD, October, 1982.
2. Andresen, P.L., 1989. Mechanisms and modeling of water chemistry effects in inconels and stainless, low alloy and carbon steels in high temperature water. Paper 566, Corrosion 89. National Association of Corrosion Engineers, New Orleans, LA, April, 1989.
3. Andresen, P.L., 1991. Fracture mechanics data and modeling of environmental cracking of nickel-base alloys in high temperature water. Paper 44, Corrosion 91. National Association of Corrosion Engineers, Cincinnati, OH, March, 1991.
4. Andresen, P.L., 1992. In: Jones, R.H. (Ed.), Stress Corrosion Cracking-Material Performance and Evaluation. ASM, Materials Park, pp. 181-210.
5. Andresen, P.L., 1995a. Mitigation of stress corrosion cracking by underwater thermal spray coating of noble metals. Paper 412, Corrosion 95. National Association of Corrosion Engineers, Orlando, FL, March, 1995.
6. Andresen, P.L., 1995b. Application of noble metal technology for mitigation of stress corrosion cracking in BWRs. In: Proc. 7th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. National Association of Corrosion Engineers.
7. Andresen, P.L., Ford, F.P., 1989. Modeling of irradiation effects on stress corrosion cracking growth rates. Paper 497, Corrosion 89. National Association of Corrosion Engineers, New Orleans, LA, April, 1989.
8. Andresen, P.L., Ford, F.P., 1995. Irradiation assisted stress corrosion cracking: from modeling and prediction of laboratory and in-core response to component life prediction. Paper 419, Corrosion 95. National Association of Corrosion Engineers, Orlando, FL, March, 1995.
9. Andresen, P.L., Ford, F.P., Murphy, S.M., Perks, J.M., 1990. State of knowledge of radiation effects on environmental cracking in light water reactor core materials. In: Proc. 4th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. National Association of Corrosion Engineers.
10. Angel, T., 1954. Formation of martensite in austenitic stainless steel. J. Iron Steel Inst. 177, 165-174.
11. Briant, C.L., 1984. Fundamental microstructural investigation of nuclear grade stainless steel. In: Proc. 2nd Semin, on Countermeasures for Pipe Cracking in BWRs, vol. 2, NP-3684-SR. EPRI, Palo Alto, CA, September 1984.
12. Brown, K.S., Gordon, G.M., 1987. Effects of BWR coolant chemistry on the propensity for IGSCC initiation and growth in creviced reactor internals components. In: Proc. 3rd Int. Symp. on Degradation of Materials in Nuclear Power Systems-Water Reactors, Traverse City, MI, August 1987.
13. Cowan, R.L., Gordon, G.M., 1977. Proc. Stress Corrosion Cracking and Hydrogen Embrittlement of Iron Base Alloys. Unieux-Firminy, France, 12th-16th June, 1973 (National Association of Corrosion Engineers, Houston, 1977).
14. Cowan, R.L., Kiss, E., 1993. Optimizing BWR water chemistry. In: Proc. 6th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. San Diego, CA, 1993.
15. Ford, F.P., 1986. Mechanistic interpretation of design and evaluation codes environmentally assisted cracking. Paper 327, Corrosion 86. National Association of Corrosion Engineers, Houston, TX, March, 1986.
16. Ford, F.P., Andresen, P.L., 1987. The theoretical prediction of the effect of system variables on the cracking of stainless steel and its use in design. Paper 83, Corrosion 87. National Association of Corrosion Engineers, San Francisco, CA, March, 1987.
17. Ford, F.P., Andresen, P.L., 1989. Stress corrosion cracking of low alloy steels. Paper 498, Corrosion 89. National Association of Corrosion Engineers, New Orleans, LA, April, 1989.
18. Ford, F.P., 1990. Models and Predictions of Environmentally Assisted Cracking. Corrosion Sous Contrainte, Les Editions de Physique.
19. Garzarolli, F., Rubel, H., Steinberg, E., 1984. Proc. Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. National Association of Corrosion Engineers.
20. Gordon, G.M., Brown, K.S., 1990. In: Proc. 4th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. National Association of Corrosion Engineers, pp. 14-46-14-62.
21. Gott, K., 1995. Using materials research results in new regulations - the Swedish approach. 7th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. National Association of Corrosion Engineers, pp. 639-648.
22. Hanninen, H., Aho-Mantilla, I., 1988. Proc. Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. AIME, pp. 72-92.
23. Hettiarachchi, S., Wozadlo, G.P., Andresen, P.L., Diaz, T.P., Cowan, R.L., 1995. The concept of noble metal chemical addition technology for IGSCC mitigation of structural materials. Proc. 7th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. National Association of Corrosion Engineers, pp. 735-744.
24. Horn, R.M. et al., 1982. The growth and stability of stress corrosion cracking in large diameter piping. EPRI NP-2472, July 1982.
25. Jacobs, A.J., Wozadlo, G.P., 1985. Irradiation-assisted stress corrosion cracking as a factor in nuclear power plant aging. Int. Conf. on Nuclear Power Plant Aging, Availability Factor and Reliability Analysis. American Society of Metals, p. 173.
26. Jacobs, A.J., Clausing, R.E., Miller, M.K., Shepard, C., 1990. Influence of grain boundary composition on the IASCC susceptibility of type 348 stainless steel. In: Proc. 4th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. National Association of Corrosion Engineers, pp. 14-21-14-20.
27. Kim, Y.J., Niedrach, L.W., Indig, M.E., Andresen, P.L., 1992a. J. Metals 44 (2), 14-18.
28. Kim, Y.J., Niedrach, L.W., Andresen, P.L., 1992b. Effect of hydrogen peroxide on ECP of stainless steels in 288°C water. General Electric Corporate Research and Development Laboratory Report WCWG-G-429.
29. Klepfer, H.H. et al., 1975. Cause of cracking in austenitic stainless steel piping. General Electric Company, 1975 (NEDO-2100).
30. Norris, D.I.R., Baker, C., Tischmarsh, J.M., 1986. Compositional profiles at grain boundaries in 20% Cr/25% Ni/Nb stainless steel. Proc. Radiation Induced Sensitization of Stainless Steels. Berkeley Nuclear Laboratories, pp. 86-98.
31. U.S. Nuclear Regulatory Commission, 1979. Investigation and evaluation of stress corrosion cracking in piping of light water reactor plants. US Nuclear Regulatory Commission, May 1979 (NUREG-0531).
32. Was, G.S., Andresen, P.L., 1992. J. Metals 44 (2), 8-13.