Exploratory neutronic evaluation on the enhancement of tritium breeding and energy multiplication capability using (Th,U)O2 in a solid-state tritium breeding blanket of a fusion demonstration reactor
R&D of a Li2TiO3 pebble bed for a test blanket module in JAEA
Neutron and thermal calculation of blanket for high power operating condition of fusion reactor
Neutronic analyses of design issues affecting the tritium breeding performance in different DEMO blanket concepts