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Oxidative dissolution of Cr-doped UO2 nuclear fuel. (2023)

First Author: Smith H

Attributed to: Platform for Long-term Experimental Investigation of Alteration in Disposal Environments and Storage - PLEIADES funded by EPSRC

Abstract

No abstract provided

Bibliographic Information

Digital Object Identifier: http://dx.doi.org/10.1038/s41529-023-00347-4

PubMed Identifier: 37041969

Publication URI: http://europepmc.org/abstract/MED/37041969

Type: Journal Article/Review

Volume: 7

Parent Publication: Npj Materials degradation

Issue: 1

ISSN: 2397-2106