Microstructure response and lead-bismuth eutectic corrosion behavior of 11Cr1Si ferritic/martensitic steel after Au-ion irradiation-Reference-Cited by-同舟云学术

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Microstructure response and lead-bismuth eutectic corrosion behavior of 11Cr1Si ferritic/martensitic steel after Au-ion irradiation

Published:2022-04 Issue: Volume:198 Page:110101
ISSN:0010-938X
Container-title:Corrosion Science
language:en
Short-container-title:Corrosion Science

Author:

Chen Qingsong,Bai Fan,Wang Peng,Yang Jian,Zhu Changda,Zhang Wei,Liu Hao,Zhong Yilong,Deng Jiuguo,Liu Ning,Yang Jijun

Funder

National Natural Science Foundation of China

Publisher

Elsevier BV

Subject

General Materials Science,General Chemical Engineering,General Chemistry

Reference81 articles.

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

2. Ferritic/martensitic steels for next-generation reactors;Klueh;J. Nucl. Mater.,2007

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

4. Structural materials challenges for advanced reactor systems;Yvon;J. Nucl. Mater.,2009

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

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