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논문 기본 정보

자료유형
학술저널
저자정보
유선오 (Korea Institute of Nuclear Safety) 조민기 (Korea Institute of Nuclear Safety) 이경원 (Korea Institute of Nuclear Safety) 백경록 (Korea Institute of Nuclear Safety)
저널정보
한국압력기기공학회 한국압력기기공학회 논문집 한국압력기기공학회 논문집 제16권 제1호
발행연도
2020.6
수록면
11 - 21 (11page)

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초록· 키워드

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This study aims to develop and advance the evaluation technology for assessing PHWR safety. For this purpose, the complete loss of AC power or station blackout (SBO) was selected as a target accident scenario and the analysis model to evaluate the plant responses was envisioned into the MARS-KS input model. The model includes the main features of the primary heat transport system with a simplified model for the horizontal fuel channels, the secondary heat transport system including the shell side of steam generators, feedwater and main steam line, and moderator system. A steady state condition was achieved successfully by running the present model to check out the stable convergence of the key parameters. Subsequently, through the SBO transient analyses two cases with and without the coolant leakage via the PHTS pumps were simulated and the behaviors of the major parameters were compared. The sensitivity analysis on the amount of the coolant leakage by varying its flow area was also performed to investigate the effect on the system responses. It is expected that the results of the present study will contribute to upgrading the evaluation technology of the detailed thermal hydraulic analysis on the SBO transient of the operating PHWRs.

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ABSTRACT
1. 서론
2. 중수로 원전 계통 모델링
3. 해석결과
4. 결론
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