Transactions of the Korean Society of Pressure Vessels and Piping (한국압력기기공학회 논문집)

Korean Society of Pressure Vessels and Piping (한국압력기기공학회)
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Evaluation of Creep Behaviors of Alloy 690 Steam Generator Tubing Material

Alloy 690 증기발생기 전열관 재료의 크리프 거동 평가

  • 김종민 (한국원자력연구원 안전재료기술개발부) ;
  • 김우곤 (한국원자력연구원 안전재료기술개발부) ;
  • 김민철 (한국원자력연구원 안전재료기술개발부)
  • Received : 2019.11.27
  • Accepted : 2019.12.11
  • Published : 2019.12.30
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Abstract

In recent years, attention has been paid to the integrity of steam generator (SG) tubes due to severe accident and beyond design basis accident conditions. In these transient conditions, steam generator tubes may be damaged by high temperature and pressure, which might result in a risk of fission products being released to the environment due to the failure. Alloy 690 which has increased the Cr content has been replaced for the SG tube due to its high corrosion resistance against stress corrosion cracking (SCC). However, there is lack of research on the high temperature creep rupture and life prediction model of Alloy 690. In this study, creep test was performed to estimate the high temperature creep rupture life of Alloy 690 using tube specimens. Based on manufacturer's creep data and creep test results performed in this study, creep life prediction was carried out using the Larson-Miller (LM) Parameter, Orr-Sherby-Dorn (OSD) parameter, Manson-Haford (MH) parameter, and Wilshire's approach. And a hyperbolic sine (sinh) function to determine master curves in LM, OSD and MH parameter methods was used for improving the creep life estimation of Alloy 690 material.

Keywords

References

  1. USNRC, 1998, "Risk Assessment of Severe Accident-Induced Steam Generator Tube Rupture," U. S. Nuclear Regulatory Commission, Washington, DC, NUREG-1570.
  2. Sancaktar, S., Salay, M., Lyengar, R., Azarm, A. and Majumdar, S., 2016, "Consequential SGTR Analysis for Westinghouse and Combustion Engineering Plants with Thermally Treated Alloy 600 and 690 Steam Generator Tubes," U. S. Nuclear Regulatory Commission, Washington, DC, NUREG-2195.
  3. Larson, F. R. and Miller, J., 1952, "A Time-Temperature Dependence Relationship for Rupture and Creep Stresses," Trans. ASME, Vol. 74, pp. 765-771.
  4. Penny, R. K. and Marriott, D. L, 1995, Design for Creep, London, Chapman & Hall Company, pp. 200-213.
  5. Wilshire, B. and Scharning, P. J., 2008, "A New Methodology for Analysis of Creep and Creep Fracture Data for 9-12% Chromium Steels," Int. Mater. Rev., Vol. 53, pp. 91-104. doi:https://doi.org/10.1179/174328008X254349.
  6. Wilshire, B. and Scharning, P. J., 2008, "Prediction of Long Term Creep Data for Forging 1Cr-1Mo-0.25V Steel," Mater. Sci. Tech-lond., Vol. 243, pp. 1-9. doi:https://doi.org/10.1179/174328407X245779.
  7. Wilshire, B. and Bache, M. R., 2009, "Cost Effective Prediction of Creep Design Data for Power Plant Steels," 2nd ECCC Creep Conference, Zurich, Switzerland, pp.44-55.
  8. www.specialmetals.com, 2009, Publication Number SMC-079.
  9. Kim, W. G., Park, J. Y., Kim, E. S. and Jang, J. S., 2018, "Improvement of Long-term Creep Life Extrapolation Using a New Master Curve for Grade 91 Steel," J. Mech. Sci. Technol., Vol. 32, No. 9, pp. 4165-4172. doi:https://doi.org/10.1007/S12206-018-0814-4