The complete oxidation of nuclear graphite waste via thermal treatment: An alternative to geological disposal (2018)
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.2018.05.002
Publication URI: http://dx.doi.org/10.1016/j.jnucmat.2018.05.002
Type: Journal Article/Review
Parent Publication: Journal of Nuclear Materials