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Cracking Behavior of Containment Wall of Nuclear Power Plant Reactor
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 Title & Authors
Cracking Behavior of Containment Wall of Nuclear Power Plant Reactor
Cho, Jae-Yeol; Kim, Nam-Sik; Cho, Nam-So; Choi, In-Kil;
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Tension tests of six half-thickness concrete containment wall elements were conducted as a part of Korea Atomic Energy Research Institute (KAERI) program. The aim of the KAERI test program is to provide a test-verified analytical method for estimating capacities of concrete reactor containment buildings under internal overpressurization from postulated degraded core accidents. The data from the tests reported herein should be useful for benchmarking analytical method that require modeling of material behavior including concrete cracking behavior and reinforcement/concrete interaction exhibited by the test. Major test variable is compressive strength of concrete, and its effect on the behavior of prestressed concrete panel subjected to biaxial tension is investigated.
containment wall;cracking behavior;compressive strength;prestressed concrete;biaxial tension;
 Cited by
2축 인장을 받는 철근콘크리트의 구성방정식,조재열;김남식;조남소;전영선;

한국콘크리트학회논문집, 2003. vol.15. 1, pp.69-77 crossref(new window)
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한국환경기술학회지, 2015. vol.16. 1, pp.99-107
체적제어법을 이용한 원자로 격납구조물의 경로의존형 비선형 해석,송하원;이준희;심별;변근주;

대한토목학회논문집, 2004. vol.24. 1A, pp.1-8
Path-dependent nonlinear analysis of a concrete reactor containment vessel subjected to internal pressure using a volume control technique, Engineering Structures, 2009, 31, 4, 990  crossref(new windwow)
KHNP 사이버홍보실 ' /fra_cyber.html,' 2002

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정원기 외, '격납건물 안전성 향상 기술개발 (세부과제: 프리스트레스트 콘크리트 격납건물 부재실험),' 1차년도 최종보고서, KAERI, CM-420, 2000

조재열 외, '2축 인장을 받는 철근 콘크리트의 구성방정식,' 한국콘크리트학회 논문집, Vol.15, No.1, 2002, pp.69-77