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 ...

.............................................................................................................................. iii FOREWORD ............................................................................................................................. V LIST OF FIGURES ....................................................................................................................

As part of an I-NERI project to develop safety analysis codes and experimental validation for a VeryHigh Temperature Gas-Cooled Reactor (VHTGR), we have developed MCNP5 [1] models to represent material heterogeneities inherent in the microsphere fuel particles and fuel compacts for a GT-MHR design [2]. We have also performed preliminary coupled nuclear-thermalhydraulic (NTH) analysis to obtain ...