Modelling of the effect of dislocation channel on intergranular microcrack nucleation in pre-irradiated austenitic stainless steels during low strain rate tensile loading-Reference-Cited by-同舟云学术

Modelling of the effect of dislocation channel on intergranular microcrack nucleation in pre-irradiated austenitic stainless steels during low strain rate tensile loading

Published:2010-10 Issue:2 Volume:405 Page:83-94
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Evrard Pierre,Sauzay Maxime

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference75 articles.

1. Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals

2. Deformation mechanisms in 316 stainless steel irradiated at 60°C and 330°C

3. Deformation mode maps for tensile deformation of neutron-irradiated structural alloys

4. Irradiation hardening behavior of polycrystalline metals after low temperature irradiation

5. Irradiation damage in 304 and 316 stainless steels: experimental investigation and modeling. Part II: Irradiation induced hardening

Cited by 30 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Fracture properties of austenitic stainless steel grain boundaries oxidized in PWR environment;Acta Materialia;2024-10

2. Micromechanical mechanism of creep secondary crack propagation behavior for superalloy;Journal of Alloys and Compounds;2024-04

3. The synergistic effect between fluoridation degradation and dislocation sliding on stress corrosion failure of Monel 400 alloy in HF vapor;Corrosion Science;2023-11

4. Modelling Irradiation Effects in Metallic Materials Using the Crystal Plasticity Theory—A Review;Crystals;2023-05-05

5. Precipitation behavior and corrosion properties of friction stir welded AA5083 Al Mg alloy after sensitization;Materials Characterization;2023-05