Inhibitory effect of dislocation on helium irradiation induced damage in Fe-9 wt.Cr alloy-Reference-Cited by-同舟云学术

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Inhibitory effect of dislocation on helium irradiation induced damage in Fe-9 wt.Cr alloy

Published:2020-12 Issue: Volume:161 Page:111978
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Zhang Zhaokuan,Zhu Te,Jin Shuoxue^ORCID,Zhang Peng,Kuang Peng,Guo Liping,An Xudong,Wang Baoyi,Yu Runsheng,Zhang Shasha,Cao Xingzhong^ORCID

Funder

National Natural Science foundation of China

Natural Science Foundation of Jiangsu Province, China

China Post-doctoral Science Foundation

Publisher

Elsevier BV

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering

Reference32 articles.

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

2. Materials challenges for ITER – current status and future activities;Barabash;J. Nucl. Mater.,2007

3. High-Chromium Ferritic and Martensitic Steels for Nuclear Applications;Klueh,2001

4. Current status and future R&D for reduced-activation ferritic/martensitic steels;Hishinuma;J. Nucl. Mater.,1998

5. Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure;Garner;J. Nucl. Mater.,2000

Cited by 1 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Effect of dislocation on helium irradiation defects in low-activation martensitic steel;Acta Physica Sinica;2023

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