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Title |
Cracking Behavior of Containment Wall of Nuclear Power Plant Reactor
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Keywords |
격납건물; 인장실험; 균열거동; 압축강도; 2축 인장; 프리스트레스트 콘크리트 tension test ; containment wall; cracking behavior; compressive strength; prestressed concrete; biaxial tension |
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Abstract |
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
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