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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2021.12
- 수록면
- 3,990 - 4,002 (13page)
- DOI
- https://doi.org/10.1016/j.net.2021.06.039
이용수
초록· 키워드
오류제보하기
CSPACE (Core meltdown, Safety and Performance Analysis CodE for nuclear power plants) for a simulation of severe accident progression in a Pressurized Water Reactor (PWR) is developed by coupling ofverified system thermal hydraulic code of SPACE (Safety and Performance Analysis CodE for nuclearpower plants) and core damage progression code of COMPASS (Core Meltdown Progression AccidentSimulation Software). SPACE is responsible for the description of fluid state in nuclear system nodes,while COMPASS is responsible for the prediction of thermal and mechanical responses of core fuels andreactor vessel heat structures. New heat transfer models to each phase of the fluid, flow blockage, coriumbehavior in the lower head are added to COMPASS. Then, an interface module for the data transferbetween two codes was developed to enable coupling. An implicit coupling scheme of wall heat transferwas applied to prevent fluid temperature oscillation. To validate the performance of newly developedcode CSPACE, we analyzed typical severe accident scenarios for OPR1000 (Optimized Power Reactor1000), which were initiated from large break loss of coolant accident, small break loss of coolant accident, and station black out accident. The results including thermal hydraulic behavior of RCS, coredamage progression, hydrogen generation, corium behavior in the lower head, reactor vessel failure werereasonable and consistent. We demonstrate that CSPACE provides a good platform for the prediction ofsevere accident progression by detailed review of analysis results and a qualitative comparison with theresults of previous MELCOR analysis.
목차
등록된 정보가 없습니다.
참고문헌 (15)
참고문헌 신청
Michael Z. Podowski / 2019 / COMPASS - New modeling and simulation approach to PWR in-vessel accident progression / Nuclear Engineering and Technology 51(8):1916~1938
J. H. Bae / 2017 / Core degradation simulation of the PHEBUS FPT3 experiment using COMPASS code / Nucl. Eng. Des 320:258~268
S. J. Ha / 2011 / Development of the SPACE code for nuclear power plants / Nucl. Eng. Technol 43(5):44~62
이동규 / 2020 / Investigation of a best oxidation model and thermal margin analysis at high temperature under design extension conditions using SPACE / Nuclear Engineering and Technology 52(4):742~754
Yongjae Lee / 2017 / Efficacy assessment of independent severe accident mitigation measures in OPR1000 using MELCOR code / J. Nucl. Sci. Technol 54(1):89~100
J. H. Bae / 2017 / Core degradation simulation of the PHEBUS FPT3 experiment using COMPASS code / Nucl. Eng. Des 320:258~268
S. J. Ha / 2011 / Development of the SPACE code for nuclear power plants / Nucl. Eng. Technol 43(5):44~62
이동규 / 2020 / Investigation of a best oxidation model and thermal margin analysis at high temperature under design extension conditions using SPACE / Nuclear Engineering and Technology 52(4):742~754
Yongjae Lee / 2017 / Efficacy assessment of independent severe accident mitigation measures in OPR1000 using MELCOR code / J. Nucl. Sci. Technol 54(1):89~100
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