Evaluation of loads on the main joint of reactor pressure vessel under hypothetical severe accident at VVER-1200 NPP

Abstract This paper presents the results of calculations of the loadings that reactor main joint may experience after energetic fuel-coolant interaction in a hypothetical severe accident at VVER-1200 reactor. Estimates of the loadings are performed using a semi-empirical procedure with conservative assumptions. The initial data for estimates are deduced from the modeling of representative severe accident with an integral code SOCRAT/V1. The loadings can be used for further thermomechanical calculations of the integrity of elements that are fixing the upper head of VVER-1200 RPV.