.:. Consultation > Par auteurs du labo > Delaunay .:.

1 document

Leaching behaviour of unirradiated High Temperature Reactor (HTR) UO$_2$-ThO$_2$ mixed oxide fuel particles Landesman C., Delaunay S., Grambow B. Dans Scientific Basis for Nuclear Waste Management XXVII - Scientific Basis for Nuclear Waste Management XXVII, Suède [in2p3-00069021 - version 1]