A fracture mechanics analysis of the PWR nuclear power plant reactor pressure vessel beltline weld

In this paper, a generic pressured water reactor (PWR) power plant reactor vessel is analyzed. The primary purpose of this work is to assure structura l integrity of the irradiated reactor pressure vessel (RPV) beltline weld u nder normal operating conditions at the end-of-life, as specified by the re quirements of 10CFR50, App.G. It is found that suitable margins of safety a re maintained at the end-of-life (32 effective full power years or 1.25 x 1 0(23) n/m(2) inner wall fluence). (C) 2001 Elsevier Science B.V. All rights reserved.