Analytical work of nuclear reactor pressure vessel rupture size enlargement during severe accidents = 중대사고시 원자로 압력 용기 파손 크기 확장에 관한 해석적 연구

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In order to analyze the FCI, MCCI, and DCH, information on the vessel ablation diameter is essentially needed. In this study, we developed the ablation model using heat balance equations for molten corium flow, crust layer, and molten wall film, respectively. Also we proposed the calculation method in order to determine the heat transfer coefficient applicable for molten corium discharge out of the reactor vessel using CFD calculation. It is based on the external turbulent correlation multiplied by the correction factor determined by CFD analysis considering real geometry and real materials. In order to reflect the effect of the crust formation on the molten wall film layer, the critical molten wall thickness concept was introduced and obtained by CFD. The ablation model was well validated with a mean error of 9.34% which is much smaller than those from the model of MELCOR. Also we investigated the impacts of the current model on the penetration-depth during FCI and containment pressure during DCH in real nuclear power plants.
Advisors
No, Hee Cheonresearcher노희천researcher
Description
한국과학기술원 :원자력및양자공학과,
Publisher
한국과학기술원
Issue Date
2018
Identifier
325007
Language
eng
Description

학위논문(석사) - 한국과학기술원 : 원자력및양자공학과, 2018.2,[v, 60 p. :]

Keywords

severe accidents▼areleasing molten corium▼apressure vessel rupture▼arupture enlargement▼aex-vessel phenomena; 중대사고▼a노심 용융물 분출▼a원자로 용기 파손▼a파손 직경 확장▼a노외 현상

URI
http://hdl.handle.net/10203/266543
Link
http://library.kaist.ac.kr/search/detail/view.do?bibCtrlNo=733942&flag=dissertation
Appears in Collection
NE-Theses_Master(석사논문)
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