Design Criteria for Fracture Assessment of Pressurized Nuclear Components

Abstract

This paper presents the design criteria adopted for fracture assessment of pressurized components of nuclear power plants. Although there are wide variety of components in a typical nuclear power plant, the thrust in this paper is on components which are part of the primary heat transport system. The paper presents an overview of design rules, practices adopted and experimental verification needed for ensuring the structural integrity of nuclear pressure vessels and piping.