The Liquid-Salt-Cooled Very High-Temperature Reactor (LS-VHTR) was modeled using the neutronics analysis code SCALE6.0 and thermal-hydraulics kinetics modeling RELAP5-3D with objective to devise, analyze, evaluate feasibility stability of a start-up procedure for this reactor natural circulation coolant under Loss Of Offsite Power (LOOP) conditions. This Generation IV design has been initially ...

This paper analyzes natural circulation flow in solid breeder blanket designs with poloidal coolant channels under a LOFA condition. Analyses couple the flow transient behaviors with transient heat transport models. While two-phase natural circulation exists in the system, a homogenous mixture model is used. The results of example calculations performed for an ITER solid breeder design concept ...