Microstructure evolution of modified 310S austenitic stainless steels under argon ion irradiation at different temperatures-Reference-Cited by-同舟云学术

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Microstructure evolution of modified 310S austenitic stainless steels under argon ion irradiation at different temperatures

Published:2019-11 Issue: Volume:459 Page:7-14
ISSN:0168-583X
Container-title:Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms
language:en
Short-container-title:Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms

Author:

Wei Yaxia,Shen Zhenyu,Zhang Weiping,Tang Rui,Long Yunxiang,Chen Cheng,Zhou Xiong,Guo Liping,Qiu Shui

Funder

National Natural Science Foundation of China

International Science & Technology Cooperation Program of China

Publisher

Elsevier BV

Subject

Instrumentation,Nuclear and High Energy Physics

Reference35 articles.

1. Effect of dissolved oxygen content on the oxide structure of Alloy 625 in supercritical water environments at 700 °C;Chang;Corros. Sci.,2014

2. Characterization of oxide scales grown on alloy 310S stainless steel after long term exposure to supercritical water at 500 °C;Behnamian;Mater. Charact.,2016

3. Materials challenges in nuclear energy;Zinkle;Acta Mater.,2013

4. Supercritical water-cooled reactor materials – summary of research and open issues;Guzonas;Prog. Nucl. Energy.,2014

5. Structural materials for Gen-IV nuclear reactors: challenges and opportunities;Murty;J. Nucl. Mater.,2008

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1. In-situ TEM investigation of dislocation loop evolution in HR3 steel during Fe+ ion irradiation;Journal of Nuclear Materials;2023-05

2. Variation in nanopillar surface on plasma-etched stainless steel owing to the crystal phase and composition;Materials Chemistry and Physics;2021-11

3. Extended damage range of (Al0.3Cr0.2Fe0.2Ni0.3)3O4 high entropy oxide films induced by surface irradiation*;Chinese Physics B;2020-06-01

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