Irradiation-induced impurity segregation and ductile-to-brittle transition temperature shift in high chromium ferritic/martensitic steels
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference17 articles.
1. R.L. Klueh, D.R. Harries, High chromium ferritic and martensitic steels for nuclear application, ASTM MONO3, West Conshohocken, PA, 2001.
2. Grain boundary impurity segregation and neutron irradiation effects in ferritic alloys
3. Control of phosphorus inter-granular segregation in ferritic steels
4. Radiation-induced segregation in HT-9 martensitic steel
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1. Irradiation embrittlement in pure chromium and chromium-tungsten alloy in a view of their potential application for fusion plasma facing components;Journal of Nuclear Materials;2021-10
2. Theoretical models for irradiation hardening and embrittlement in nuclear structural materials: a review and perspective;Acta Mechanica Sinica;2020-02-27
3. Fracture features of heat-resistant 12% Cr ferritic-martensitic steel EK-181 in the temperature range of its ductile-brittle transition;PROCEEDINGS OF THE INTERNATIONAL CONFERENCE ON PHYSICAL MESOMECHANICS. MATERIALS WITH MULTILEVEL HIERARCHICAL STRUCTURE AND INTELLIGENT MANUFACTURING TECHNOLOGY;2020
4. Radiation induced segregation in quaternary Fe-Ti-Y-O alloys;Journal of Alloys and Compounds;2017-04
5. Irradiation effects in Generation IV nuclear reactor materials;Structural Materials for Generation IV Nuclear Reactors;2017
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