Investigative Study of Neutronic Safety Parameters of HPR and EPR Using the MCNP Code

Abstract

As part of technology assessment of proposed commercial nuclear power reactor technologies for Ghana’s Nuclear Power Programme, the neutronic safety parameters of the European Pressurized Reactor (EPR) and High Temperature Pressurized Reactor (HPR) reactor technologies are theoretically analyzed and compared. The MCNP neutronic code was employed as a computational tool to analyze the reactivity temperature coefficients, moderator void coefficient, criticality, and neutron behavior at various operating conditions. The HPR, which is still under construction and under theoretical safety analysis, showed good inherent safety features comparable to the already existing EPR technology.