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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 저널정보
- 국제구조공학회 Structural Engineering and Mechanics, An Int'l Journal Structural Engineering and Mechanics, An Int'l Journal Vol.60 No.2
- 발행연도
- 2016.1
- 수록면
- 337 - 350 (14page)
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초록· 키워드
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Even though extensive researches have been performed for steam explosion due to their complex mechanisms and inherent uncertainties, establishment of severe accident management guidelines and strategies is one of state-of-the arts in nuclear industry. The goal of this research is primarily to examine effects of vessel failure modes and locations on nuclear facilities under typical steam explosion conditions. Both discrete and integrated models were employed from the viewpoint of structural integrity assessment of steel components and evaluation of the cracking and crushing in reinforced concrete structures. Thereafter, comparison of systematic analysis results was performed; despite the vessel failure modes were dominant, resulting maximum stresses at the all steel components were sufficiently lower than the corresponding yield strengths. Two failure criteria for the reinforced concrete structures such as the limiting failure ratio of concrete and the limiting strains for rebar and liner plate were satisfied under steam explosion conditions. Moreover, stresses of steel components and reinforced concrete structures were reduced with maximum difference of 12% when the integrated model was adopted comparing to those of discrete models.
목차
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참고문헌 (19)
참고문헌 신청
2010 / ACI Committee 349, Code requirements for nuclear safety related concrete structures / American Concrete Institute
Chunyu, Z. / 2014 / Evaluation of the structural integrity of the CPR1000 PWR containment under steam explosion accidents / Nucl. Eng. Des 278:632~643
Cizelj, L. / 2006 / Vulnerability of a partially flooded PWR reactor cavity to a steam explosion / Nucl. Eng. Des 236:1617~1627
Cullis, I.G. / 2010 / Assessment of blast loading effects-Types of explosion and loading effects / Int. J. Press. Ves. Pip 87:493~503
Hu, H.T. / 2006 / Ultimate analysis of PWR prestressed concrete containment subjected to internal pressure / Int. J. Press. Ves. Pip 83:161~167
Chunyu, Z. / 2014 / Evaluation of the structural integrity of the CPR1000 PWR containment under steam explosion accidents / Nucl. Eng. Des 278:632~643
Cizelj, L. / 2006 / Vulnerability of a partially flooded PWR reactor cavity to a steam explosion / Nucl. Eng. Des 236:1617~1627
Cullis, I.G. / 2010 / Assessment of blast loading effects-Types of explosion and loading effects / Int. J. Press. Ves. Pip 87:493~503
Hu, H.T. / 2006 / Ultimate analysis of PWR prestressed concrete containment subjected to internal pressure / Int. J. Press. Ves. Pip 83:161~167
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