8 records found
1
Mechanical behaviour of macro-dispersed interet matrix fuels
Present status in the Netherlands of research relevant to High Temperature Gas-Cooled Reactor design
Post irradiation examination of uranium inclusions in inert matrices
Present status in the Netherlands of research relevant to High-Temperature Gas-Cooled Reactor design
Fission gas release in a spinel-based fuel used for actanide transmutation
On the irradiation performance of HCPB candidate ceramic breeder materials to DEMO-like conditions - An approach with neutron and particle irradiations
Neutron irradiation of polycrystalline yttrium aluminate garnet, magnesium aluminate spinel and alpha-alumina