DOI QR코드

DOI QR Code

Stress Corrosion Crack Rate of STS 304 Stainless Steel in High Temperature Water

고온수중에서 STS 304 스테인리스강의 응력부식균열 성장속도

  • Published : 2000.01.01

Abstract

Sensitized STS 304 stainless steel crack growth rate(CGR) in high temperature water was investigated under trapezoidal wave loading test using fracture mechanics techniques. The CGR, due to stress corrosion cracking(SCC), were systematically measured as a function of the stress intensity factor and stress. holding time under trapezoidal wave loading. In high temperature water, CGR was enhanced by a synergistic effects in combination with an aggressive environment and mechanical damage. The CGR, $(da/dN)_{env}$ was basically described as a summation of the environmentally assisted crack growth rate $(da/dN)_{SCC}$, $(da/dN)_{CF}$ and fatigue crack growth rate in air $(da/dN)air,. The CGR, $(da/dN)_{env}$, increased linearly with increasing stress holding time. The CGR, $(da/dN)_{SCC}$ decreased linearly with increasing stress holding time. Fracture surface mode varied from trans-granular cracking to inter-granular cracking with increasing stress holding time.

Keywords

Corrosion Fatigue(CF;Environmentally Assisted Crack(EAC;Crack Growth Rate(CGR;Time Based Analysis(TBA;Stress Corrosion Crack(SCC

References

  1. 橫堀 武夫, 1989, '先端材科强度と破壞におけゐ疑問点とその解決へのアプロ-チ,' 일본금속학회 회보, 제23권, 제9호, pp. 703-704
  2. Andresen, P. L., 1981, 'Innovations in Experimental Techniques for Testing in High Temperature Aqueous Environments,' Technical Infomation Series, 81 CRD088, General Electric, N.Y., p. 4
  3. Shack, W. J., Kassner, T. F., 1994, 'Review of Environmental Effects on Fatigue Crack Growth of Austenitic Stainless Steels,' NUREG /CR-6176, ANL-94/1, p. 7
  4. Ford, F. P, Taylor, D. F. and Andresen, P. L., 1987, 'Corrosion Assisted Crackin of Stainless and Low Alloy Steels in LWR Environments,' EPRI NP-5046M, Project 2006-6, Final Report, pp. 210
  5. Kawakubo, T., Hisida, M., Amano, K., and Katsuta, M., 1980, 'Crack Growth Behavior of Type 304 Stainless Steel in Oxygenated $290^{\circ}C$ Pure Water Under Low Frequency Cyclic Loading,' Corrosion, Vol. 369, No. 11, pp. 638-647
  6. 森谷 信一, 1995, '輕水爐壓力壁部材の 應力 食割れ擧動の定 予測に關する硏究,' 日本 東北大學校 博士學位論文, 仙台市, p. 2-25
  7. ASTM E 399, 1991, 'Standard Test Method for Plane-Strain Fracture Toughness of Metallic Materials.'
  8. Gabetta, G and Torronen, K., 1985, 'Prediction of Cyclic Crack Growth Rate in L WR Environments,' Proc. of 2nd IAEA Specialists' Meeting on Subcritical Crack Growth, Vol.2, Sendai, May 13-15, pp. 131-154
  9. ASME, 1991, ASME PVRC Program on Code Criteria for Cyclic Life and Environmental Effects (draft 3)
  10. 庄子 哲雄 外, 1994, 火力 原子力および化學 プラント機器 構造部材の年劣化と壽命予測, リアライズ社, 東京都, p. 29
  11. Ford, F. P. and Emigh, P. W., 1995, 'The Prediction of The Maximum Corrosion Fatigue Crack Propagation Rate in The Low Alloy Steel de-Oxygenated Water System at $288^{\circ}C$,' Corrosion Science, Vol. 25, No. 8/9, pp. 673-692
  12. 김 영진 외, 1996, '원자력배관 건전성평가 전문가 시스템 개발(1)-평가법 제시 및 재료물성치추론,' 대한기계학회논문집(A), 제20권 제2호, pp. 575-584
  13. 이 강용 외, 1997, '원자력발전소 가압기 밀림관 노즐의 잔존 피로수명평가,' 대한기계학회논문집(A), 제21권, 제8호, pp. 1259-1269
  14. 정 순억, 1997, '국산 원자로용기 재료의 피로 및 파괴특성 연구,' 대한기계학회논문집(A), 제21권, 제10호, pp. 1626-1635
  15. 小林 英男, 1992, '經年孫復の非破壤評價と壽命予測,' 安全工學, 제31권, 제2호, p. 76