Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Validation of applicability of induction bending process to P91 piping of prototype Gen-IV sodium-cooled fast reactor (PGSFR)

  • Tae-Won Na (Korea Atomic Energy Research Institute (KAERI)) ;
  • Nak-Hyun Kim (Korea Atomic Energy Research Institute (KAERI)) ;
  • Chang-Gyu Park (Korea Atomic Energy Research Institute (KAERI)) ;
  • Jong-Bum Kim (Korea Atomic Energy Research Institute (KAERI)) ;
  • Il-Kwon Oh (Department of Mechanical Engineering, Korea Advanced Institute of Science and Technology (KAIST))
  • Received : 2023.02.21
  • Accepted : 2023.06.12
  • Published : 2023.10.25
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Abstract

The application of the induction bending process to pipe systems in various industrial fields is increasing. Recently, efforts have also been made to apply this bending process to nuclear power plants because it can innovatively reduce welded parts of the curved pipes, such as elbows. However, there have been no cases of the application of induction bending to the piping of nuclear power plants. In this study, the applicability of the P91 induction bending piping for the sodium-cooled fast reactor PGSFR was validated through high temperature low cycle fatigue tests and creep tests using P91 induction bending pipe specimens. The tests confirmed that the materials sufficiently satisfied the fatigue life and the creep rupture life requirements for P91 steel at 550 ℃ in the ASME B&PV Code, Sec. III, Div. 5. The results show that the effects of heating and bending by the induction bending process on the material properties were not significant and the induction bending process could be applicable to piping system of PGSFR well.

Keywords

Acknowledgement

This work was supported by a grant from the National Research Foundation of Korea (NRF) funded by the Korean government (Ministry of Science and ICT) (NRF-2021M2E2A1037872).

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