Intergranular stress distributions in polycrystalline aggregates of irradiated stainless steel

JOURNAL OF NUCLEAR MATERIALS

卷:476

Article

Hure, J.¹  El Shawish, S.²  Cizelj, L.²  Tanguy, B.¹ 

[1] Univ Paris Saclay, CEA, Serv Etud Mat Irradies, DEN, F-91191 Gif Sur Yvette, France

[2] Jozef Stefan Inst, SI-1000 Ljubljana, Slovenia

关键词: Stress corrosion cracking;    Irradiation hardening;    Crystal plasticity;    Finite element simulations;   

DOI  :  10.1016/j.jnucmat.2016.04.017

来源: Elsevier

【 摘 要 】

In order to predict InterGranular Stress Corrosion Cracking (IGSCC) of post -irradiated austenitic stainless steel in Light Water Reactor (LWR) environment, reliable predictions of intergranular stresses are required. Finite elements simulations have been performed on realistic polycrystalline aggregate with recently proposed physically -based crystal plasticity constitutive equations validated for neutron irradiated austenitic stainless steel. Intergranular normal stress probability density functions are found with respect to plastic strain and irradiation level, for uniaxial loading conditions. In addition, plastic slip activity jumps at grain boundaries are also presented. Intergranular normal stress distributions describe, from a statistical point of view, the potential increase of intergranular stress with respect to the macroscopic stress due to grain -grain interactions. The distributions are shown to be well described by a master curve once rescaled by the macroscopic stress, in the range of irradiation level and strain considered in this study. The upper tail of this master curve is shown to be insensitive to free surface effect, which is relevant for IGSCC predictions, and also relatively insensitive to small perturbations in crystallographic texture, but sensitive to grain shapes. (C) 2016 Elsevier B.V. All rights reserved.

【 授权许可】

Free