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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2021.3
- 수록면
- 812 - 824 (13page)
- DOI
- https://doi.org/10.1016/j.net.2020.08.003
이용수
초록· 키워드
오류제보하기
In order to reduce risks from the Steam Generator Tube Rupture (SGTR) accident and to meet safetytargets, various measures have been analyzed to minimize the amount of fission product (FP) release. Inthis paper, we propose an introduction of a Containment Filtered Venting System (CFVS) connected tothe steam generator secondary side, which can reduce the amount of FP release while minimizingadverse effects identified in the previous studies. In order to compare the effect of new equipment withthe existing strategy, accident simulations using MELCOR were performed. As a result of simulations, it isconfirmed that CFVS operation lowers FP release into the environment, and the release fractions arelower (minimum 0.6% of the initial inventory for Cs) than that of the strategy which intends todepressurize the primary system directly (minimum 15.2% for Cs). The sensitivity analyses identify thatrefill of the CFVS vessel is a dominant contributor reducing the amount of FP released. As the newstrategy has the possibility of hydrogen combustion and detonation in CFVS, the installation of an igniterinside the CFVS vessel may be considered in reducing such hydrogen risk.
목차
등록된 정보가 없습니다.
참고문헌 (17)
참고문헌 신청
S.A. Eide / 2007 / NUREC/CR-6928:Industry-Average Performance for Components and Initiating Events at US Commercial Nuclear Power Plants :42
Nuclear Safety and Security Commission / 2017 / Regulation on the Scope of Accident Management and the Detailed Criteria for Evaluating Accident Management Capabilities. Notice No. 2017-2034
R. J. Lutz / 1994 / Westinghouse Owners Group Severe Accident Management Guidance Validation
Wonjun Choi / 2017 / Effectiveness and adverse effects of in-vessel retention strategies under a postulated SGTR accident of an OPR1000 / Journal of Nuclear Science and Technology :1~11
T. Kim / A conceptual approach to eliminate bypass release of fission products by in-containment Relief valve under SGTR accident / Sci. Technol. Nucl. Ins
Nuclear Safety and Security Commission / 2017 / Regulation on the Scope of Accident Management and the Detailed Criteria for Evaluating Accident Management Capabilities. Notice No. 2017-2034
R. J. Lutz / 1994 / Westinghouse Owners Group Severe Accident Management Guidance Validation
Wonjun Choi / 2017 / Effectiveness and adverse effects of in-vessel retention strategies under a postulated SGTR accident of an OPR1000 / Journal of Nuclear Science and Technology :1~11
T. Kim / A conceptual approach to eliminate bypass release of fission products by in-containment Relief valve under SGTR accident / Sci. Technol. Nucl. Ins
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