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논문 기본 정보

자료유형
학술저널
저자정보
Sung-Hyun Kang (KEPCO International Nuclear Graduate School (KINGS)) Shin Eom (KEPCO International Nuclear Graduate School (KINGS)) Aya Diab (KEPCO International Nuclear Graduate School (KINGS)) Seung-Jong Oh (KEPCO International Nuclear Graduate School (KINGS))
저널정보
한국전산유체공학회 한국전산유체공학회지 한국전산유체공학회지 제22권 제4호
발행연도
2017.12
수록면
55 - 66 (12page)
DOI
10.6112/kscfe.2017.22.4.055

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초록· 키워드

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Since the Fukushima Dai-ichi NPP accident, the Korean regulatory agency as well as the US NRC have strengthened the SBO mitigation capability for all operating and new reactors as a part of the defense-in-depth measure. In this paper, the multi-dimensional analysis of reactor safety (MARS) code is used to model APR1400 under the extended SBO condition. A thermal hydraulic analysis is undertaken to ascertain the plant"s coping capability for up to 72 hours if a set of diverse and flexible coping strategies (FLEX) is implemented as proposed by the American nuclear energy institute, NEI[1]. Notably, for the extended SBO, the RCP seal leakage is an important yet uncertain parameter that may significantly affect the thermal hydraulic response of the plant. Given the significance and uncertainty of the RCP seal leakage rates on the plant"s response, a parametric study is conducted for different leakage rates. The plant"s response to the extended SBO with attendant RCP seal leakage solely relying on the existing equipment is first examined. Subsequently, an optimized coping strategy using the additional FLEX equipment (primary-side and secondary-side external injection) is developed with different RCP seal leakage rates for up to 72 hours into the accident.

목차

1. Introduction
2. Methodology
3. Result and Discussion
4. Conclusion
References

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UCI(KEPA) : I410-ECN-0101-2018-559-001740197