Description of the PLINIUS prototypic experimental platform and the safety issues relative to the operation of the platform
Advances of Study on Thermal/Hydraulic Performance in Tight-Lattice Rod Bundles for Reduced-Moderation Water Reactors
Intermediate Evaluation of a Feasibility Study Project on Commercialized Fast Reactor Cycle Systems in Japan
Thermal-Hydraulic Design For Reactor Upper Plenum And Large Diameter Piping For An Innovative Sodium-Cooled Fast Reactor