In-situ WB-STEM observation of dislocation loop behavior in reactor pressure vessel steel during post-irradiation annealing-Reference-Cited by-同舟云学术

In-situ WB-STEM observation of dislocation loop behavior in reactor pressure vessel steel during post-irradiation annealing

Published:2020-08 Issue: Volume:12 Page:100778
ISSN:2589-1529
Container-title:Materialia
language:en
Short-container-title:Materialia

Author:

Du Yufeng,Yoshida Kenta,Shimada Yusuke^ORCID,Toyama Takeshi,Inoue Koji,Arakawa Kazuto,Suzudo Tomoaki^ORCID,Milan Konstantinovic J.,Gerard Robert,Ohnuki Somei,Nagai Yasuyoshi

Publisher

Elsevier BV

Subject

General Materials Science

Reference52 articles.

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3. On the history and status of reactor pressure vessel steel ductile to brittle transition temperature shift prediction models;Odette;J. Nucl. Mater.,2019

4. Weak-beam scanning transmission electron microscopy for quantitative dislocation density measurement in steels;Yoshida;Microscopy,2017

5. Contribution of irradiation-induced defects to hardening of a low copper reactor pressure vessel steel;Shimodaira;Acta Mater.,2018

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