Void swelling in high dose ion-irradiated reduced activation ferritic–martensitic steels-Reference-Cited by-同舟云学术

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Void swelling in high dose ion-irradiated reduced activation ferritic–martensitic steels

Published:2015-07 Issue: Volume:462 Page:119-125
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Wang Xu,Monterrosa Anthony M.,Zhang Feifei,Huang Hao,Yan Qingzhi,Jiao Zhijie,Was Gary S.,Wang Lumin

Publisher

Elsevier BV

Subject

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

Reference33 articles.

1. Ferritic/martensitic steels for next-generation reactors

2. The challenge of developing structural materials for fusion power systems

3. Progress in development of China Low Activation Martensitic steel for fusion application

4. Status of R&D on fusion materials in institute of nuclear materials in USTB

5. First results of characterization of 9Cr-3WVTiTaN low activation ferritic/martensitic steel

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1. Void swelling in pure iron after sequential self-ion-irradiation at different energies: Effect of injected interstitials and additional damage in regions containing pre-existing voids;Journal of Nuclear Materials;2024-09

2. Ferritic–Martensitic Steels in Power Industry: Microstructure, Degradation Mechanism, and Strengthening Methods;steel research international;2024-08-26

3. Formation of < 100 > vacancy dislocation loops from two-dimensional vacancy platelets in body-centered cubic iron;Journal of Materials Science;2024-04

4. In-situ study on factors impeding dislocation motion in Fe9Cr1.5W0.4Si F/M steel during high temperature heating;Materials Science and Engineering: A;2024-01

5. Enhanced irradiation tolerance of a medium entropy alloy via precipitation and dissolution of nanoprecipitates;Journal of Nuclear Materials;2023-12

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