Numerical simulations of Quasi-Static Fracture Behaviour of AISI 316 for Nuclear Transport packages

Abstract

Nuclear transport packages must pass stringent post-design safety tests before they can be licensed for use. Impact and thermal tests are designed to replicate the worst case conditions in the event of an accident, and often result in the failure of some materials. The outer construction of nuclear transport packages relies on AISI 316. Finite element (FE) models help demonstrate part of the testing required for the performance of nuclear transport packages. FE codes accurately predict the elastic-plastic response of materials up to the ultimate tensile strength. In this study, preliminary work of a series of 12 specimens are designed for numerical simulations using the FE code ABAQUS on AISI 316. The evolution of stress triaxiality during multiaxial loading conditions such as tensile, compressive, pure shear and combined loading conditions is used to further understand ductile fracture.