Analytical Studies of the Actual Scale Steel Containment Vessel Model

摘要

Nuclear Power Engineering Colporation (NUPEC) of Japan and Nuclear Regulartoly Comittee (NRC) of the US havernjointly sponsored "Structural Behavior Test" in "Cooperative Containment Research Program" to investigate the response ofrnrepresentative models of nuclear reactor containment structure due to internal pressure loading beyond the design basisrnaccident and to establish analytical prediction methods.rnIn this paper, we summarized application of the analytical prediction method based on the above tests and analyses tornan actual scale steel containment vessel (SCV) model under the severe accident condition. First, we conducted whole modelrnanalysis under the severe accident condition (in this case, high pressure and elevated temperature). As the result, high strainrnwas observed around suppression chamber hatch, so we selected the area around it as a target of submodel (detailed model)rnanalysis. We also utilized the whole model analysis result as boundaiy conditions.