Critical heavy water level and some parameters for the HWZPR reactor core using MCNP4c code

Abstract

The MCNP4c code, based on the probabilistic approach, is applied in modeling the 3D configuration of the Heavy Water Zero Power Reactors (HWZPRs) core. All of the constituents of the core such as fuel pellets, fuel elements, moderator (D2O) and annular graphite reflector are simulated using the MCNP4c code. The benchmark calculations are made to estimate various parameters including effective multiplication factor (Keff), number of neutron production per fission (ν), and energy release in the fuel per fission (Q). The (n,Xn) reaction with changes in water level are investigated. In order to validate the MCNP4c calculations, the obtained critical water level is compared to that of the experimental data. Good consistency is observed between calculated and experimental data.