📣 Help Shape the Future of UKRI's Gateway to Research (GtR)

We're improving UKRI's Gateway to Research and are seeking your input! Tell us what works, what doesn't, and how we can make GtR more user-friendly, impactful, and effective for the Research and Innovation community. Please send your feedback to gateway@ukri.org by 11 August 2025.

Modelling the interaction of primary irradiation damage and precipitates: Implications for experimental irradiation of zirconium alloys (2018)

First Author: Adrych-Brunning A

Attributed to: Enhancing nuclear fuel efficiency through improved understanding of irradiation damage in zirconium cladding funded by EPSRC

Abstract

No abstract provided

Bibliographic Information

Digital Object Identifier: http://dx.doi.org/10.1016/j.jnucmat.2017.10.022

Publication URI: http://dx.doi.org/10.1016/j.jnucmat.2017.10.022

Type: Journal Article/Review

Parent Publication: Journal of Nuclear Materials