Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Assessment of thermal fatigue induced by dryout front oscillation in printed circuit steam generator

  • Kwon, Jin Su (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology) ;
  • Kim, Doh Hyeon (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology) ;
  • Shin, Sung Gil (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology) ;
  • Lee, Jeong Ik (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology) ;
  • Kim, Sang Ji (Korea Atomic Energy Research Institute)
  • Received : 2021.03.08
  • Accepted : 2021.09.02
  • Published : 2022.03.25
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Abstract

A printed circuit steam generator (PCSG) is being considered as the component for pressurized water reactor (PWR) type small modular reactor (SMR) that can further reduce the physical size of the system. Since a steam generator in many PWR-type SMR generates superheated steam, it is expected that dryout front oscillation can potentially cause thermal fatigue failure due to cyclic thermal stresses induced by the transition in boiling regimes between convective evaporation and film boiling. To investigate the fatigue issue of a PCSG, a reference PCSG is designed in this study first using an in-house PCSG design tool. For the stress analysis, a finite element method analysis model is developed to obtain the temperature and stress fields of the designed PCSG. Fatigue estimation is performed based on ASME Boiler and pressure vessel code to identify the major parameters influencing the fatigue life time originating from the dryout front oscillation. As a result of this study, the limit on the temperature difference between the hot side and cold side fluids is obtained. Moreover, it is found that the heat transfer coefficient of convective evaporation and film boiling regimes play an essential role in the fatigue life cycle as well as the temperature difference.

Keywords

Acknowledgement

This work was supported by the National Research Foundation of Korea (NRF), South Korea grant funded by the Korean Government (MIST). (No. 2018M2A8A4081307) and supported by the KAI-NEET Institute, South Korea, KAIST, Korea. (N11210064). We also would like to acknowledge the technical support from ANSYS Korea, South Korea.

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