Nuclear Engineering and Technology

  • 제53권2호
  • /
  • Pages.666-676
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  • 2021
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  • 1738-5733(pISSN)
  • /
  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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Burst pressure estimation of Alloy 690 axial cracked steam generator U-bend tubes using finite element damage analysis

  • Kim, Ji-Seok (Korea University, Department of Mechanical Engineering) ;
  • Kim, Yun-Jae (Korea University, Department of Mechanical Engineering) ;
  • Lee, Myeong-Woo (Korea Atomic Energy Research Institute, Innovative SMR System Development Division) ;
  • Jeon, Jun-Young (Korea Institute of Materials Science, Authorized Nuclear Inspection Department) ;
  • Kim, Jong-Sung (Sejong University, Department of Nuclear Engineering)
  • 투고 : 2020.02.20
  • 심사 : 2020.07.16
  • 발행 : 2021.02.25
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초록

This paper presents numerical estimation of burst pressures of axial cracked U-bend tubes, considering the U-bending process analysis. The validity of the FE simulations is confirmed by comparing with published experimental data. From parametric analyses, it is shown that existing EPRI burst pressure estimation equations for straight tubes can be conservatively used to estimate burst pressures of the U-bend tubes. This is due to the increase in yield strength during the U-bending process. The degree of conservatism would decrease with increasing the bend radius and with increasing the crack depth.

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과제정보

This study was supported by Korea Institute of Energy Technology Evaluation and Planning (KETEP) (No. 20171520101650).

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피인용 문헌

  1. Effect of Tensile Stress on the Oxide Properties of a Nickel-Based Alloy 600 in Simulated PWR Secondary Water vol.14, pp.21, 2021, https://doi.org/10.3390/ma14216460