Proceedings of the Korean Nuclear Society Conference (한국원자력학회:학술대회논문집)

Korean Nuclear Society (한국원자력학회)
권호 표지

Comparison of auxiliary Feedwater and EDRS Operation during Natural Circulation of MRX

  • Kim, Jae-Hak (Seoul National University Department of Nuclear Engineering) ;
  • Park, Goon-Cherl (Seoul National University Department of Nuclear Engineering)
  • Published : 1997.05.01
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Abstract

The MRX is an integral type ship reactor with 100 MWt power, which is designed by Japan Atomic Energy Research Institute. It is characterized by integral type PWR, in-vessel type control roe drive mechanism, water-filled containment vessel and passive decay heat removal system. Marine reactor should have high passive safety. Therefore, in this study, we simulated the loss of flow accident to verify the passive decay heat removal by natural circulation using RETRAN-03 code. auxiliary feed water systems are used for decay heat removal mechanism and results are compared with the loss of flow accident analysis using emergency decay heat removal system by JAERI. Results are very similar to case of EDRS 1 loop operation in JAERI analysis and decay heat is successfully removed by natural circulation.

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