Nuclear Engineering and Technology

  • 제51권7호
  • /
  • Pages.1805-1815
  • /
  • 2019
  • /
  • 1738-5733(pISSN)
  • /
  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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Crack growth rate evaluation of alloys 690/152 by numerical simulation of extracted CT specimens

  • Lee, S.H. (R&D Institute of Radioactive Wastes, Korean Radioactive Waste Agency) ;
  • Kim, S.W. (Nuclear Material Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Cho, C.H. (R&D Institute of Radioactive Wastes, Korean Radioactive Waste Agency) ;
  • Chang, Y.S. (Department of Nuclear Engineering, Kyung Hee University)
  • 투고 : 2019.02.13
  • 심사 : 2019.05.12
  • 발행 : 2019.10.25
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초록

While nickel-based alloys have been widely used for power plants due to corrosion resistance and good mechanical properties, during the last couple of decades, failures of nuclear components increased gradually. One of main degradation mechanisms was primary water stress corrosion cracking at dissimilar metal welds of piping and reactor head penetrations. In this context, precise estimation of welding effects became an important issue for ensuring reliability of them. The present study deals with a series of finite element analyses and crack growth rate evaluation of Alloys 690/152. Firstly, variation of residual stresses and equivalent plastic strains was simulated taking into account welding of a cylindrical block. Subsequently, extraction and pre-cracking of compact tension (CT) specimens were considered from different locations of the block. Finally, crack growth curves of the alloys and heat affected zone were developed based on analyses results combined with experimental data in references. Characteristics of crack growth behaviors were also discussed in relation to mechanical and fracture parameters.

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과제정보

연구 과제 주관 기관 : National Research Foundation (NRF), Korea Institute of Energy Technology Evaluation and Planning

참고문헌

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