Author(s)

P. Dupas & D. Moinereau

Abstract

Reactor pressure vessels are internally clad with austenitic stainless steel. This welding operation generates residual stresses which can have an important role in integrity assessments. In order to evaluate these stresses, an experimental and numerical programme has been conducted. The experiments includes cladding operations, macrographic analyses, temperature and residual stresses measurements. Finite element calculations were used to simulate both welding operations and post weld heat treatment. These calculations coupled the thermal, metallurgical and mechanical aspects in a 2D representation. 1 Introduction A research programme was started in 1987 at EDF, concerning flaw assesment in nuclear reactor pressure vessels, and more particula

Keywords