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Sensitivity Study on Creep Behaviors of RPV under Severe Accident conditions

중대사고 조건하의 원자로용기 크리프 거동 민감도 분석 연구

  • Received : 2016.11.25
  • Accepted : 2017.06.29
  • Published : 2017.06.30

Abstract

Reactor pressure vessel (RPV) under severe accident conditions accompanied by core melting is exposed to direct high-temperature thermal loads. Understanding the creep behavior of the material is one of the most important factors for evaluating the structural integrity at these conditions. While damage evaluation studies have been conducted on critical structures of nuclear power plants through finite element (FE) analyses considering creep behavior, for accurate creep damage evaluation, constitutive equations considered in the FE analyses may have different results depending on the time hardening and strain hardening models as well as the tertiary creep consideration. The purpose of this study is to evaluate the creep damage under severe accident conditions by using FE method for a representative domestic RPV material, SA508 Gr.3. The effect of material hardening models and constitutive equations which are the main variables were also investigated.

Keywords

References

  1. U. S. Department of Energy, "In-Vessel Coolability and Retention of a Core Melt", DOE/ID-10460, 1993.
  2. U.S.NRC, "Lower Head Failure Experiments and Analyses", NUREG/CR-5582, 1999.
  3. OECD/NEA, OECD Lower head failure project final report, Vol. 1 - integral experiments and material characterization, 2002.
  4. ABAQUS User's Manual, Ver.6-14, Dassault Systems, 2015.
  5. T. H. Kim, S. H. Kim and Y. S. Chang, "Structural Assessment of Reactor Pressure Vessel under Multi-Layered Corium Formation Conditions", Nuclear Engineering and Technology, 47, 351-361, 2015. https://doi.org/10.1016/j.net.2014.12.017
  6. Core (MELCOR) Package Reference Manual, NUREG/CR-6119, Rev. 2, 2001.
  7. L. J. Xie, X. Ren, M. X. Shen and L. Q. Tu, "Parameter correlation of high-temperature creep constitutive equation for RPV metallic materials, Journal of Nuclear Materials, 465, 196-203, 2015. https://doi.org/10.1016/j.jnucmat.2015.05.032
  8. H. Altenbach, K. Naumenko, "Modeling of creep for structural analysis", Springer, 2006.