PREDICTIONS OF ULTIMATE LOAD CAPACITY FOR PRE-STRESSED CONCRETE NUCLEAR CONTAINMENT VESSEL MODEL WITH BARC FINITE ELEMENT CODE ULCA

摘要

BARC participated in a round robin analysis activity to predict the ultimate load capacity of a 1:4 size nuclear containment vessel model cosponsored jointly by Sandia National Laboratory, Nuclear Regulatory Commission, USA and Nuclear Power Engineering Corporation, Japan. The test model represents a PWR steel line pre-stressed concrete containment located at Ohi station in Japan. BARC in-house finite element code ULCA (Ultimate Load Capacity Assessment) predictions are reported in this paper, which are shown to have very good comparison with the experimental ultimate capacity test concluded recently by Sandia laboratory.