Liquid-salt-cooled Reactor Start-up with Natural Circulation

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 developed by Oak Ridge National Laboratory studied researchers worldwide almost decade. While analyses have previously performed show performance during normal operation shutdown scenarios, no study heretofore published examine active or passive reactor. fuel temperature (Doppler) density coefficient reactivity LSVHTR were examined CSAS6 module code. Negative Doppler feedback coefficients calculated. Two initial RELAP5 simulations obtain steady-state conditions model predict changes thermal-hydraulic parameters Next, series step additions core simulated determine how much can be inserted without jeopardizing safety core. Finally, developed, restart convection simulated. results demonstrated potential LS-VHTR.