A review of irradiation effects on LWR core internal materials – IASCC susceptibility and crack growth rates of austenitic stainless steels
Source abstract
Abstract
Austenitic stainless steels (SSs) are used extensively as structural alloys in the internal components of light water reactor (LWR) pressure vessels because of their relatively high strength, ductility, and fracture toughness. However, exposure to neutron irradiation for extended periods changes the microstructure (radiation hardening) and microchemistry (radiation-induced segregation) of these steels, and degrades their fracture properties. Irradiation-assisted stress corrosion cracking (IASCC) is another degradation process that affects LWR internal components exposed to neutron radiation. The existing data on irradiated austenitic SSs were reviewed to evaluate the effects of key parameters such as material composition, irradiation dose, and water chemistry on IASCC susceptibility and crack growth rates of these materials in LWR environments. The significance of microstructural and microchemistry changes in the material on IASCC susceptibility is also discussed. The results are used to determine (a) the threshold fluence for IASCC and (b) the disposition curves for cyclic and IASCC growth rates for irradiated SSs in LWR environments.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Hydrogen embrittlement and corrosion behaviors in metals · Fusion materials and technologies · Nuclear Materials and Properties
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (68)
Show source-provided references
1. Bruemmer · 1996
2. Scott · J. Nucl. Mater. · 1994 · 211 · 10110.1016/0022-3115(94)90360-3 ↗
3. P. L. Andresen, F.P. Ford, S.M. Murphy, J.M. Perks, in: Proc. 4th Intl. Symp. on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, NACE, Houston, TX, 1990, pp. 1.83–1.121.
4. G.S. Was, P.L. Andresen, Corrosion, vol. 63, Paper No. 1, NACE, Houston, TX, 2007.
5. K.S. Brown, G.M. Gordon, in: Proc. Third Intl. Symp. on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactor, Metallurgical Society, Warrendale, PA, 1987, pp. 243–248.
6. G.M. Gordon, K.S. Brown, in: Daniel Cubicciotti (Ed.), Proc. 4th Intl. Symp. on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactor, NACE, Houston, TX, 1990, pp. 14.46–14.61.
7. F. Garzarolli, D. Alter, P. Dewes, in: Proc. Intl. Symp. on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactor, American Nuclear Society, Lagrange, IL, 1986, pp. 131–138.
8. M. Kodama et al., in: R.E. Gold, E.P. Simonen (Eds.), Proc. Sixth Intl. Symp. on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactor, Minerals, Metals & Materials Society, Warrendale, PA, 1993, pp. 583–588.
9. M. Kodama et al., in: Proc. Fifth Intl. Symp. on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactor, American Nuclear Society, Lagrange, IL, 1991, pp. 948–954.
10. W.L. Clark, A.J. Jacobs, in: Proc. First Intl. Symp. on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactor, NACE, Houston, TX, 1983, p. 451.
11. A.J. Jacobs, G.P. Wozadlo, K. Nakata, T. Yoshida, I. Masaoka, in: Proc. Third Intl. Symp. on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactor, Metallurgical Society, Warrendale, PA, 1987, pp. 673–681.
12. H.M. Chung, W.J. Shack, NUREG/CR-6892, ANL-04/10, 2006.
13. P.L. Andresen, Corrosion/02, Paper No. 02509, NACE, Houston, TX, 2002.
14. P.L. Andresen, F.P. Ford, Corrosion/95, Paper No. 419, NACE, Houston TX, 1995.
15. Stoenescu · 2005 · 267
16. Jenssen · 1995 · 1043
17. Jenssen · 1993 · 547
18. Ford · 1994 · 501
19. P.L. Andresen, in: Proc. Research Topical Symposium on Environmental Cracking, Corrosion/07, NACE, Houston, TX, 2007.
20. P.L. Andresen, M.M. Morra, in: T.R. Allen, P.J. King, L. Nelson (Eds.), Proc. 13th Intl. Conf. on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Paper No. P0124, Canadian Nuclear Society, Toronto, Canada, 2007.
21. Bruemmer · J. Nucl. Mater. · 1999 · 274 · 29910.1016/S0022-3115(99)00075-6 ↗
22. Maziasz · J. Nucl. Mater. · 1993 · 205 · 11810.1016/0022-3115(93)90077-C ↗
23. Zinkle · J. Nucl. Mater. · 1993 · 206 · 26610.1016/0022-3115(93)90128-L ↗
24. Edwards · J. Nucl. Mater. · 2003 · 317 · 1310.1016/S0022-3115(03)00002-3 ↗
25. S.M. Bruemmer, D.J. Edwards, B.W. Arey, L.A. Charlot, in: Proc. Ninth Intl. Symp. on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactor, Metallurgical Society, Warrendale, PA, 1999, pp. 1079–1087.
26. S.M. Bruemmer, in: Proc. Tenth Intl. Symp. on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactor, Paper No. 0008V, NACE, Houston, TX, 2001.
27. Lee · 1981 · 191
28. Lucas · J. Nucl. Mater. · 1993 · 206 · 28710.1016/0022-3115(93)90129-M ↗
29. Y. Chen, O.K. Chopra, W.K. Soppet, N.L. Dietz Rago, W.J. Shack, in: T.R. Allen, P.J. King, L. Nelson (Eds.), Proc. 13th Intl. Conf. on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Paper No. P0026, Canadian Nuclear Society, Toronto, Canada, 2007.
30. J.C. Van Duysen, P. Todeschini, G. Zacharie, in: 16th International Symposium on Effects of Radiation on Materials, American Society for Testing and Materials, ASTM STP 1175, 1993, pp. 747–776.10.1520/STP23969S ↗
31. W.S. Hazelton, W.H. Koo, NUREG-0313, Rev. 2, 1988.
32. O.K. Chopra, B. Alexandreanu, E.E. Gruber, R.S. Daum, W.J. Shack, NUREG/CR-6891, ANL-04/20, 2006.
33. O.K. Chopra, W.J. Shack, NUREG/CR-6960, ANL-06/58, March 2008.
34. Ooki · 2005 · 365
35. Andresen · 2005 · 87
36. Edwards · 2005 · 419
37. D. Edwards, E. Simonen, S. Bruemmer, in: T.R. Allen, P.J. King, L. Nelson (Eds.), Proc. 13th Intl. Conf. on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Paper No. P0139, Canadian Nuclear Society, Toronto, Canada, 2007.
38. Materials Reliability Program A Review of Radiation Embrittlement for Stainless Steels (MRP-79), Rev. 1, EPRI Report 1008204, September 2004.
39. A. Demma, R. Carter, A. Jenssen, T. Torimaru, R. Gamble, in: T.R. Allen, P.J. King, L. Nelson (Eds.), Proc. 13th Intl. Conf. on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Paper No. 114, Canadian Nuclear Society, Toronto, Canada, 2007.
40. T.M. Karlsen, M. Espeland, A. Horvath, HWR-773, OECD Halden Reactor Project, May 2005.
41. Conermann · 2005 · 277
42. K. Takakura, K. Nakata, M. Ando, K. Fujimoto, E. Wachi, in: T.R. Allen, P.J. King, L. Nelson (Eds.), Proc. 13th Intl. Conf. on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Paper No. P0009, Canadian Nuclear Society, Toronto, Canada, 2007.
43. Materials Reliability Program Development of Material Constitutive Model for Irradiated Austenitic Stainless Steels, MRP-135, EPRI Report 1011127, Decmber 2004.
44. A. Jenssen, K. Gott, P. Efsing, P.O. Andersson, in: Proc. 11th Intl. Symp. on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, vol. 20, American Nuclear Society, Lagrange, IL, 2003, pp. 1015–1024.
45. T. Nakamura, M. Koshiishi, T. Torimaru, Y. Kitsunai, K. Takakura, K. Nagata, M. Ando, Y. Ishiyama, A. Jenssen, in: T.R. Allen, P.J. King, L. Nelson (Eds.), Proc. 13th Intl. Conf. on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Paper No. P0, Canadian Nuclear Society, Toronto, Canada, 2007.
46. R. Sumiya, S. Tanaka, K. Nakata, K, Takakura, M. Ando, T. Torimaru, Y. Kitsunai, in: T.R. Allen, P.J. King, L. Nelson (Eds.), Proc. 13th Intl. Conf. on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Paper No. P0072, Canadian Nuclear Society, Toronto, Canada, 2007.
47. Andresen · Trans. ASME · 2007 · 129 · 488
48. R. Pathania, R. Carter, R. Horn, P. Andresen, in: Proc. 14th Intl. Conf. on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Paper No. 203178, American Nuclear Society, Lagrange Park, IL, 2009.
49. T.M. Karlsen, A. Horvath, HWR-770, OECD Halden Reactor Project, December 2004.
50. J. Nakano, T.M. Karlsen, M. Espeland, HWR-862, OECD Halden Reactor Project, February 2007.
51. Karlsen · 2005 · 337
52. Jenssen · 2009
53. O.K. Chopra, E.E. Gruber, W.J. Shack, NUREG/CR-6826, ANL-03/22, 2003.
54. Chopra · 2005 · 289
55. J. Nakano, T.M. Karlsen, M. Espeland, HWR-843, OECD Halden Reactor Project, August 2008.
56. R.B. Davis, P. Andresen, Cooperative IASCC Research (CIR) Final Report, EPRI 1007378, October 2002.
57. L.A. James, D.P. Jones, in: R. Rungta (Ed.), Proc. Conf. on Predictive Capabilities in Environmentally-assisted Cracking, PVP, vol. 99, American Society of Mechanical Engineers, New York, 1985, pp. 363–414.
58. W.J. Shack, T.F. Kassner, NUREG/CR-6176, ANL-94/1, 1994.
59. P. Shahinian, H.E. Watson, H.H. Smith, NRL Report 7446, Naval Research Laboratory, Washington, DC, July 1972.
60. Shahinian · 1975 · 191
61. James · Nucl. Technol. · 1973 · 19 · 14810.13182/NT73-A15876 ↗
62. James · J. Nucl. Mater. · 1976 · 59 · 18310.1016/0022-3115(76)90133-1 ↗
63. P. Shahinian, H.E. Watson, H.H. Smith, neutron irradiation effects on fatigue crack growth in types 304 and 316 stainless steels, in: Irradiation Effects on Reactor Structural Materials, Quarterly Progress Report 1 May – 31 July 1972, NRL Memorandum Report 2505, Naval Research Laboratory, Washington, DC, August 1972, pp. 13–22.
64. Materials Reliability Program: PWR Internals Material Aging Degradation Mechanism Screening, and Threshold Values, MRP-175, EPRI Report 1012081, December 2005.
65. R.P. Shogan, T.R. Mager, in: Proc. 10th Intl. Conf. on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Paper No. 0030, NACE/ANS/TMS, Lake Tahoe, NV, 5–9 August 2001.
66. P.D. Freyer, T.R. Mager, M.A. Burke, in: T.R. Allen, P.J. King, L. Nelson (Eds.), Proc. 13th Intl. Conf. on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Paper No. P0034, Canadian Nuclear Society, Toronto, Canada, 2007.
67. H. Nishioka, K. Fukuya, K. Fujii, T. Torimaru, in: T.R. Allen, P.J. King, L. Nelson (Eds.), Proc. 13th Intl. Conf. on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, , Paper No. P0040, Canadian Nuclear Society, Toronto, Canada, 2007.
68. S. Fyfitch, H. Xu, P. Scott, L. Fournier, A. Demma, in: Proc. 14th Intl. Conf. on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, American Nuclear Society, Lagrange Park, IL, 2009.