Load consequences of reactor pressure vessel failure at high primary system pressure / Belastungen infolge Versagens eines Reaktordruckbehälters bei hohem Primärsystemdruck

Abstract

The load acting on the pressure vessel of a pressurised water reactor and its support girder after vessel failure at high primary system pressure (17 MPa) is estimated. The analysis is based on one-dimensional thermal-hydraulic calculations performed with the transient analysis code RELAP5/MOD3. The information obtained provides a force-function input for structural dynamic calculations of an increased containment for future nuclear power stations that can safely confine core-melt consequences. The computations lead to a maximum hydraulic load of 340 MN on the vessel support structure if a global circumferential rupture of the vessel lower head is assumed