Abstract:
Among the Generation IV reactors, the Very High Temperature Reactor (VHTR) is being considered as the ideal design for a Next Generation Nuclear Plant (NGNP). The VHTR system is designed for a gas cooled reactor and originates from modifying and further developing the 600MW Gas Turbine-Module Helium Reactor (GTMHR). The GT-MHR system has inherent safety features that make events leading to a severe accident significantly unlikely. The Reactor Cavity Cooling System (RCCS)
is a crucial component in passive decay heat removal using air natural convection. The PIRT (Phenomena Identification and Ranking Table) for the RCCS was developed through evaluations of physical phenomena which might arise during a LBLOCA. In addition, this study presents the basic performance for the RCCS using analytical and numerical analysis.
