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Determining the low temperature Cr solubility limit and precipitation mechanisms in Fe-Cr alloys with proton irradiations and thermal aging (2025)

First Author: Zhao Y

Attributed to: Fusion Reactor Shielding Materials (FURESHMA): Understanding In-service Degradation funded by EPSRC

Abstract

No abstract provided

Bibliographic Information

Digital Object Identifier: http://dx.doi.org/10.1016/j.matdes.2025.114280

Publication URI: http://dx.doi.org/10.1016/j.matdes.2025.114280

Type: Journal Article/Review

Parent Publication: Materials & Design