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Irradiation Assisted Stress Corrosion Cracking of Austenitic Stainless Steels in Water Reactors

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주제분류금속공학

초록

Based upon the good compatibility to neutron irradiation and high temperature water environment, austenitic stainless steels are widely used for core internal structural materials of light water reactors. But, recently, intergranular cracking was detected in the stainless steels for the core applications in some commercial PWR plants. Authors studied on the root cause of the intergranular cracking and developed the countermeasure including the alternative materials for these core applications. The intergranular cracking in these core applications are defined as an irradiation assisted mechanical cracking and irradiation assisted stress corrosion cracking. In this paper, the root cause of the intergranular cracking and its countermeasure are summarized and discussed.

Abstract

Based upon the good compatibility to neutron irradiation and high temperature water environment, austenitic stainless steels are widely used for core internal structural materials of light water reactors. But, recently, intergranular cracking was detected in the stainless steels for the core applications in some commercial PWR plants. Authors studied on the root cause of the intergranular cracking and developed the countermeasure including the alternative materials for these core applications. The intergranular cracking in these core applications are defined as an irradiation assisted mechanical cracking and irradiation assisted stress corrosion cracking. In this paper, the root cause of the intergranular cracking and its countermeasure are summarized and discussed.

참고문헌 (18)

  1. UNIPEDE Specialists Mtg. on Life- Limiting & Regulatory Aspects of Core Internals and Pressure Vessels, "NEA", pp.1987, P. M. Scott
  2. M. P. Monahan, "Trans. of 9th SMiRTC", pp.75~ (1987)
  3. T. Matsuoka, , J. of Nuclear Science and Technology, 35, pp.564~ (1998)
  4. J. E. Moon, , the International Conference on Fontevraud III, pp.726~ (1994)
  5. C. Janssen, "Unpublished Paper", ~ (2002)
  6. K. Fujimoto, , the 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors-, pp.299~ (2005)
  7. P. L. Andresen, , the 4th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor-, pp.1~ (1990)
  8. P. Scott, , J. Nuclear Materials, 211, pp.101~ (1994)
  9. A. J. Jacobs, "Letter Report and Literature Search" (1979), GE Nuclear Energy
  10. M. Kodama, , the 5th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors-, pp.948~ (1991)
  11. R. Cauvin, , the International Conference on Fontevraud III, pp.54~ (1994)
  12. T. Yonezawa, , the International 8th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors-, pp.823~ (1997)
  13. T. Yonezawa, , the International Conference on Fontevraud IV, pp.237~ (1998)
  14. T. Yonezawa, , the Ninth International Symposium on “Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors”, pp.1015~ (1999)
  15. K. Fujimoto, , Corrosion Engineering, 49, pp.701~ (2000)
  16. T. Yonezawa, , Corrosion Engineering, 49, pp.655~ (2000)
  17. T. Yonezawa, , ASTM STP (2000)
  18. J. Conermann, , the Twelfth International Conference on “Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors”, pp.277~ (2005)

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