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Temperature and dose effects on dislocation loops in self-ion irradiated high-purity iron (2025)

First Author: Li 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.actamat.2025.121235

Publication URI: http://dx.doi.org/10.1016/j.actamat.2025.121235

Type: Journal Article/Review

Parent Publication: Acta Materialia