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학술저널
저자정보
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한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제48권 제1호
발행연도
2016.1
수록면
218 - 227 (10page)

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Background: Steam explosions may occur in nuclear power plants by molten fuelecoolantinteractions when the external reactor vessel cooling strategy fails. Since this phenomenoncan threaten structural barriers as well as major components, extensive integrity assessmentresearch is necessary to ensure their safety. Method: In this study, the influence of yield criteria was investigated to predict the failure ofa reactor cavity under a typical postulated condition through detailed parametric finiteelement analyses. Further analyses using a geometrically simplified equivalent model withhomogeneous concrete properties were also performed to examine its effectiveness as analternative to the detailed reinforcement concrete model. Results: By comparing finite element analysis results such as cracking, crushing, stresses,and displacements, the WillameWarnke model was derived for practical use, and failurecriteria applicable to the reactor cavity under the severe accident condition were discussed. Conclusion: It was proved that the reactor cavity sustained its intended function as a barrierto avoid release of radioactive materials, irrespective of the different yield criteria thatwere adopted. In addition, from a conservative viewpoint, it seems possible to employ thesimplified equivalent model to determine the damage extent and weakest points duringthe preliminary evaluation stage

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