Nuclear Engineering and Technology

  • 제56권1호
  • /
  • Pages.257-264
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  • 2024
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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Impingement wastage experiment with SUS 316 in a printed circuit steam generator

  • Siwon Seo (School of Mechanical and Control Engineering, Handong Global University Pohang) ;
  • Bowon Hwang (School of Mechanical and Control Engineering, Handong Global University Pohang) ;
  • Sangji Kim (Korea Atomic Energy Research Institute) ;
  • Jaeyoung Lee (School of Mechanical and Control Engineering, Handong Global University Pohang)
  • 투고 : 2022.11.09
  • 심사 : 2023.09.30
  • 발행 : 2024.01.25
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초록

The sodium cooled fast reactor (SFR) is one of the Gen-IV reactors with the most operating experience accumulated. Although the technology level is the most mature among the Gen-IV reactors, there is still a safety problem that has not been solved, which is the sodium-water reaction. Since sodium and water are separated only by a heat transfer tube with a thickness of only a few mm, there is inherently a risk of a sodium-water reaction (SWR) accident in the SFR. In this study, it is attempted to quantitatively evaluate the resistance of SWR accidents by replacing the shell and tube steam generator with printed circuit steam generator (PCSG) as a method to mitigate the SWR accident. To do this, a CATS-S (Compact Accident Tolerance Steam Generator-SWR) facility was designed and built. And for the quantitative evaluation of accident resistance, a methodology for measuring the impingement wastage rate was established. As a result of this research, the impingement wastage rate caused by SWR generated in a PCSG was measured first time. It was confirmed that the impingement wastage phenomenon was suppressed in the PCSG, and the accident resistance was higher than that of the SWR through comparison with the experimental results performed in the existing shell and tube steam generator. In conclusion, a PCSG is more resistant to impingement wastage as a result of the SWR accident than existing shell and tube steam generators, and it is estimated that a PCSG can mitigate SWR accidents, an inherent problem of SFR.

키워드

과제정보

This work was supported by the National Research Foundation of Korea (NRF) grant funded by the Korea government (MSIP). (No. 2017M2A8A4018624 and No. 2017M2A8A4018812).

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