Early corrosion behavior of low carbon 9Cr-ODS steel in high temperature oxygen-saturated lead-bismuth eutectic-Reference-Cited by-同舟云学术

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Early corrosion behavior of low carbon 9Cr-ODS steel in high temperature oxygen-saturated lead-bismuth eutectic

Published:2024-08 Issue: Volume:236 Page:112285
ISSN:0010-938X
Container-title:Corrosion Science
language:en
Short-container-title:Corrosion Science

Author:

Yang Chongdou,Xu Yuwen,Yun Di^ORCID,Zhao Bingyao,Liu Wenguan^ORCID,Gao Rui,Xie Shijing,Qiu Jie^ORCID

Publisher

Elsevier BV

Reference63 articles.

1. Introduction to Generation IVnuclear reactors;Buckthorpe;Struct. Mater. Gener. IV Nucl. React.,2017

2. 7 - Irradiation effects in Generation IV nuclear reactor materials;Aitkaliyeva,2017

3. GEN-IV LFR development: status & perspectives;Lorusso;Prog. Nucl. Energy,2018

4. Corrosion phenomena induced by liquid metals in Generation IV reactors;Fazio,2017

5. Enhanced radiation-tolerant oxide dispersion strengthened steel and its microstructure evolution under helium-implantation and heavy-ion irradiation;Lu;Sci. Rep.,2017

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