Dose dependence of true stress parameters in irradiated bcc, fcc, and hcp metals
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference32 articles.
1. Tensile properties of candidate SNS target container materials after proton and neutron irradiation in the LANSCE accelerator
2. Radiation embrittlement behavior of fine-grained molybdenum alloy with 0.2wt%TiC addition
3. The influence of fast neutron irradiation and irradiation temperature on the tensile properties of wrought LCAC and TZM molybdenum
4. Tensile properties and fracture mode of a wrought ODS molybdenum sheet following fast neutron irradiation at temperatures ranging from 300°C to 1000°C
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