Soldas dissimilares em reatores nucleares: revisão dos principais aspectos relacionados à soldagem dissimilar de aço carbono e aço inoxidável austenítico com adição de ligas de níquel.

Abstract

This work presents a review of the literature about Stress Corrosion Cracking, which is one of the main damage mechanisms that affect PWR and BWR type nuclear reactor. It deals with issues related to one of the sources of the problem, which are the trative residual stress caused by the thermal cycle of welding. It also addressed measurement techniques of residual stresses, with emphasis on technique the center hole drilling. It is shown that, once found the problem, there are means to mitigate the damage, which allow prolonging the life of the component.