Effect of proton irradiation and grain boundary engineering on stress corrosion cracking of ferritic-martensitic alloys in supercritical water

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

Volumn , Issue , 2005, Pages 1359-1368

  Gupta, Gaurav ^a   Was, Gary S ^a  

^a UNIVERSITY OF MICHIGAN   (United States)

Author keywords

Grain Boundary Engineering (GBE); Intergranular stress corrosion cracking (IGSCC); Super critical water (SCW)

Indexed keywords

GRAIN BOUNDARY ENGINEERING (GBE); INTERGRANULAR STRESS CORROSION CRACKING (IGSCC); SUPER CRITICAL WATER (SCW);

FAILURE ANALYSIS; FERRITE; GRAIN BOUNDARIES; MARTENSITIC TRANSFORMATIONS; SUPERCRITICAL FLUIDS; THERMAL EFFECTS;

STRESS CORROSION CRACKING;

EID: 33745243373     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (47)

1. th Environmental-Degradation of materials in nuclear systems-water reactor conference, Aug 14-18, Salt lake city, Utah.
2. P.L. Andresen, P.P. Ford, S.M. Murphy, J.M. Perks, Proc. Fourth Int'l Symp. On Environmental Degradation of Materials in Nuclear Power Systems Water Reactors, NACE, 1990, pp. 1-83 to 1-121.
3. A. J. Jacobs, Letter Report and Literature Search, GE Nuclear Energy, San Jose, CA, May, 1979.
4. F. Garzrolli, H. Rubel and E. Steinberg, in Proc. First Int'l Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE, Houston, 1984, p. 1.
5. H. Hanninen and I. Aho-Mantila, in Proc. Third Int'l Symp on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, AIME, Warrendale, 1988, p. 77.
6. V. Pasupathi and R. W. Klingensmith, "Investigation of Stress Corrosion Cracking in Clad Fuel Elements and Fuel Performance in the Connecticut Yankee Reactor," NP-2119, Electric Power Research Institute, 1981.
7. G.M. Gordon and K.S. Brown, Proc. Fourth Int'l Symp on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE, 1990, p.14-46.
8. K.S. Brown and G.M. Gordon, Proc. Third Int'l Symp on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, AIME, 1987, pp. 243-248.
9. C. F. Cheng, Corrosion 20 (1964) 341.
10. P.M. Scott, W. Foot, L.A. Goldsmith, S. Dumbill, T.M. Williams, J.M. Perks, C.A. English and W.G. Burns, in NEA/UNIPEDE Specialists Mtg on Life Limiting and Regulatory Aspects of Core Internals and Pressure Vessels, Stockholm, Oct 14-16, 1987.
11. H.M.Kim and J.A.Szpunar, Materials Science Forum Vols. 157-162, pp. 1997-2003.
12. G.palumbo et al, Mat Res. Soc. Symp. Proc. Vol.238, 1992, pp 311-316.
13. E.M.Lehockey et al, Corrosion Science 46 (2004) 2383-2404.
14. B.Alexandreanu, Ph.D Thesis; University of Michigan, 2002.
15. Gaurav Gupta, Bogdan Alexandreanu, G S Was Metallurgical and Materials Transactions; Feb 2004; 35A, Research Library pg. 717.
16. Gaurav Gupta and Gary.S.Was, Journal of ASTM International, March 2005, Vol. 2, No. 3.
17. J. F. Ziegler, SRIM 2003 program, J.P. Biersack, IBM Corp., Yorktown, NY, (2003).
18. G.Gupta et al, "Microstructural evolution of proton irradiated T91", accepted for publishing in Journal of Nuclear Materials.
19. T.R.Alien et al, Journal of ASTM International, March 2005 Vol2, No.3.
20. N. Hashimoto and R.L Klueh, "Microstructural evolution of nickel-doped 9Cr steels irradiated at HFIR," Journal of Nuclear Materials, Vol. 305, pp. 153-158,2002.
21. X. Jia et al., "Microstructure in martensitic steels T91 and F82H after irradiation in SINQ Target-3," Journal of Nuclear Materials, Vol. 318, pp. 207-214, 2003.
22. J.Gan, T.R.Allen, J.I.Cole, S.Ukai, S.Shuttanandan and S.Thevuthasan, Materials Research Society Symposium Proceedings Volume 792, (2004).
23. D. S. Gelles, "Microstructural examination of commercial ferritic alloys at 200 dpa," Journal of Nuclear Materials, Vol. 233-237, pp. 293-298, 1996.
24. R. L. Klueh et al., "Microstructure-mechanical properties correlation of irradiated conventional and reduced activation martensitic steels," Journal of Nuclear Materials,Vol. 225, pp. 175-186, 1995.
25. R.E. Clausing, L. Heatherly, R.G. Faulkner, A.F. Rowcliffe, K. Farrell, Radiation-induced segregation in HT-9 martensitic steel, Journal of Nuclear Materials, 141-143(1986)978-981.
26. T. Kato, H. Takahashi, S. Ohnuki, K. Nakata, J. Kuniya, The effect of solute content on grain boundary segregation in electron-irradiated Fe-Cr-Mn alloys, Journal of Nuclear Materials, 179-181 (1991) 623-625.
27. H. Takahashi, T. Kato, S. Watanabe, N. Sakaguchi, Grain boundary segregation under irradiation in a HVEM, Annales de Physique, 20(C3) (1995) 109-116.
28. T. S. Morgan, E. A. Little, R. G. Faulkner, and J. Titchmarsh, Effects of Radiation in Materials 15th International Symposium, ASTM STP 1125, Eds., R. E. Stoller, A. S. Kumar, and D. Gelles, (American Society for Testing and Materials, Philadelphia, 1992), p. 633.
29. P.J. Maziasz, Formation and stability of radiation-induced phases in neutron-irradiated austenitic and ferritic steels, Journal of Nuclear Materials, 169 (1989) 95-115.
30. R. L. Klueh and D. R. Harries, High-chromium Ferritic and Martensitic Steels for Nuclear Applications. MONO3, (American Society for Testing and Materials, Philadelphia, 2001).
31. R. L. Klueh and D. J. Alexander, Journal of Nuclear Materials, 187, p. 60 (1992).
32. J. T. Busby, M. C. Hash, G. S. Was, Journal of Nuclear Materials, 336, pp. 267-278 (2005).
33. W. L. Hu and D. S. Gelles, in: Influence of radiation on material properties: 13th International Symposium, ASTM STP 956, Part 2, Eds. F. A. Garner, C. H. Henager, Jr., and N. Igata, p. 83, (1987).
34. R.L.Klueh et al, Journal of Nuclear Materials 225 (1995) 175-186.
35. R.Bullough, D.R.Harries, and M.R.Hayns, J. Nucl. Mater. 88 (1980) 312.
36. J. T. Busby, M. C. Hash, G. S. Was, Journal of Nuclear Materials, 336, pp. 267-278 (2005).
37. A.Alamo, X.Averty, "Status of post-irradiation examinations performed on RA and conventional martensitic steels irradiated at 325C in Osiris reactor," Progress Report UT-SM&C-LAM2, CEA report, NT SRMA 99-2316, April 1999.
38. th Environmental-Degradation of materials in nuclear systems-water reactor conference, Aug 14-18, Salt lake city, Utah.
39. R.L.Klueh and J.M.Vitek, J.Nucl.Mater. 161, 13-23 (1989).
40. K.Shiba, I.Ioka, J.E.Robertson, M.Suzuki, and A.Hishinuma, in: Proceedings, Conference on Materials and nuclear power (The institute of materials, London, 1996)265.
41. M.B.Toloczko et al, Journal of Nuclear Materials 318 (2003) 200-206.
42. Thaveeprungsriporn, V. and Was, G. S., Metallurgical and Materials Transactions, A, 28, 1997, pp. 2101-2111.
43. Dingley, D. J. and Pond, R. C., "On the Interaction of Crystal Dislocations with Grain Boundaries," Acta Metall, 27, 1979, pp. 667-82. P.L.
44. Lojkowski, W., "On the Spreading of Grain Boundary Dislocation and Its Effect on Grain Boundary Properties," Acta Metall. Mater., 39, 8, 1991, pp. 1891-1899.
45. RD edition (John wiley & sons, Newyork, 1989)253.
46. C.J.McMohan, Jr., in: Fundamental Phenomenon in the materials sciences, vol. 4, Eds. L.J.Bonis, J.J.Duga, and J.J.Gilman (plenum press, newyork, 1967) 247.
47. H. Tanigawa, M.A. Solokov, K. Shiba, R.L. Klueh, "Charpy Impact Properties of reduced-activation ferritic/martensitic steels irradiated in HFIR up to 20 dpa", Fusion Science and Technology, 44, pp. 66-72, (2003).