The distribution and selective decontamination of carbon-14 from nuclear graphite (2021)
Attributed to:
Mechanisms of Retention and Transport of Fission Products in Virgin and Irradiated Nuclear Graphite
funded by
EPSRC
Abstract
No abstract provided
Bibliographic Information
Digital Object Identifier: http://dx.doi.org/10.1016/j.jnucmat.2021.153167
Publication URI: http://dx.doi.org/10.1016/j.jnucmat.2021.153167
Type: Journal Article/Review
Parent Publication: Journal of Nuclear Materials