Helium cavity formation research on oxide dispersed strengthening (ODS) ferritic steels utilizing dual-ion irradiation facility
Author:
Publisher
Elsevier BV
Subject
Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering
Reference10 articles.
1. Research and development of iron-based alloys for nuclear technology.
2. Perspective of ODS alloys application in nuclear environments
3. Corrosion properties of oxide dispersion strengthened steels in super-critical water environment
4. Implications of fundamental radiation damage studies in the research and development of materials for a fusion reactor
5. A new Multiple Beams–Material Interaction Research Facility for radiation damage studies in fusion materials
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1. Preferential nucleation of (O, Y/La/Ce/Hf)-core nano-clusters in multi-element micro-alloyed ferritic alloys: A first-principles study;Journal of Applied Physics;2023-08-17
2. Indentation response of model oxide dispersion strengthening alloys after ion irradiation up to 700 °C;Journal of Applied Physics;2022-11-07
3. Positron annihilation spectroscopic study of intrinsic and ion-irradiation induced vacancy defects in Zr-containing ODS steels with and without Al;J ALLOY COMPD;2022
4. Positron annihilation spectroscopic study of intrinsic and ion-irradiation induced vacancy defects in Zr-containing ODS steels with and without Al;Journal of Alloys and Compounds;2022-11
5. Highly stable nanocrystalline oxide dispersion strengthened alloys with outstanding helium bubble suppression;Journal of Nuclear Materials;2021-12
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