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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2016.1
- 수록면
- 218 - 227 (10page)
이용수
초록· 키워드
오류제보하기
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
목차
등록된 정보가 없습니다.
참고문헌 (18)
참고문헌 신청
정재훈 / 2015 / EVALUATION OF HEAT-FLUX DISTRIBUTION AT THE INNER AND OUTER REACTOR VESSEL WALLS UNDER THE IN-VESSEL RETENTION THROUGH EXTERNAL REACTOR VESSEL COOLING CONDITION / Nuclear Engineering and Technology 47(1):66~73
김태현 / 2015 / STRUCTURAL ASSESSMENT OF RPV UNDER MULTI-LAYERED CORIUM FORMATION CONDITIONS / Nuclear Engineering and Technology 47(3):351~361
S.H. Kim / 2015 / Structural assessment of fully flooded reactor cavity and penetration piping under steam explosion conditions / Int. J. Press. Vessels Pip 131:36~44
L. Cizelj / 2006 / Vulnerability of a partially flooded PWR reactor cavity to a steam explosion / Nucl. Eng. Des 236:1617~1627
I.G. Cullis / 2010 / Assessment of blast loading effects-types of explosion and loading effects / Int. J. Press. Vessels Pip 87:493~503
김태현 / 2015 / STRUCTURAL ASSESSMENT OF RPV UNDER MULTI-LAYERED CORIUM FORMATION CONDITIONS / Nuclear Engineering and Technology 47(3):351~361
S.H. Kim / 2015 / Structural assessment of fully flooded reactor cavity and penetration piping under steam explosion conditions / Int. J. Press. Vessels Pip 131:36~44
L. Cizelj / 2006 / Vulnerability of a partially flooded PWR reactor cavity to a steam explosion / Nucl. Eng. Des 236:1617~1627
I.G. Cullis / 2010 / Assessment of blast loading effects-types of explosion and loading effects / Int. J. Press. Vessels Pip 87:493~503
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