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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2019.1
- 수록면
- 1,916 - 1,938 (23page)
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The objective of this paper is to discuss the modeling principles of phenomena governing core degradation/melting and in-vessel melt relocation during severe accidents in light water reactors. The proposed modeling approach has been applied in the development of a new accident simulation package, COMPASS (COre Meltdown Progression Accident Simulation Software). COMPASS can be used either as a stand-alone tool to simulate in-vessel meltdown progression up to and including RPV failure, or as a component of an integrated simulation package being developed in Korea for the APR1400 reactor. Interestingly, since the emphasis in the development of COMPASS modeling framework has been on capturing generic mechanistic aspects of accident progression in light water reactors, several parts of the overall model should be useful for future accident studies of other reactor designs, both PWRs and BWRs. The issues discussed in the paper include the overall structure of the model, the rationale behind the formulation of the governing equations and the associated simplifying assumptions, as well as the methodology used to verify both the physical and numerical consistencies of the overall solver. Furthermore, the results of COMPASS validation against two experimental data sets (CORA and PHEBUS) are shown, as well as of the predicted accident progression at TMI-2 reactor.
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참고문헌 (15)
참고문헌 신청
D. H. Kim / 2017 / Overview of the severe accident analysis program in Korea / Proceedings of ERMSAR 2017 Conference
D. H. Kim / 1987 / The modeling of reactor pressure vessel failure modes during core meltdown accidents of BWRs / Proc. 24th National Heat Transfer Conference
S.W. Kim / 1997 / The modeling of core melting and in-vessel corium relocation in the APRIL code / Nucl. Eng. Des 177
M. Z. Podowski / 2015 / Accident Modeling Challenges and the Lessons Learned from Fukushima, Plenary Lecture / Workshop on Post-Fukushima Challenges on Severe Accident Mitigation and Research Collaboration
R.P. Taleyarkhan / 1995 / An analysis of molten-corium-induced failure of drain pipes in BWR-MARK-II containments / Chem. Eng. Commun 134
D. H. Kim / 1987 / The modeling of reactor pressure vessel failure modes during core meltdown accidents of BWRs / Proc. 24th National Heat Transfer Conference
S.W. Kim / 1997 / The modeling of core melting and in-vessel corium relocation in the APRIL code / Nucl. Eng. Des 177
M. Z. Podowski / 2015 / Accident Modeling Challenges and the Lessons Learned from Fukushima, Plenary Lecture / Workshop on Post-Fukushima Challenges on Severe Accident Mitigation and Research Collaboration
R.P. Taleyarkhan / 1995 / An analysis of molten-corium-induced failure of drain pipes in BWR-MARK-II containments / Chem. Eng. Commun 134
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