Simulated advanced gas-cooled reactor spent nuclear fuels: Determination of the O/U ratio - an XRD, XPS and Raman study (2022)
Abstract
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Bibliographic Information
Digital Object Identifier: http://dx.doi.org/10.1016/j.jnucmat.2022.153867
Publication URI: http://dx.doi.org/10.1016/j.jnucmat.2022.153867
Type: Journal Article/Review
Parent Publication: Journal of Nuclear Materials