Reactor Analysis for Counter-flowing Moderator and Coolant in a Supercritical Water Reactor

摘要

New thermal-hydraulic models have been implemented in the PARCS v2.5 core simulator to enable the simulation of heat transfer between the counter-flowing moderator and coolant in supercritical water reactors. The impact of this heat transfer on the performance of an individual assembly has been demonstrated. A quarter-core model has been simulated to demonstrate how this new capability can be used to identify hot channels in the core and to design different core configurations that may reduce the hot channel effects. Future developments will couple this core simulator capability to advanced thermal-hydraulic simulation capability for full core design and transient simulation.