Neutronics analysis code system for hybrid reactor

The configuration of the fusion driven subcritical hybrid reactor is complex, and the neutron energy spectrum varies among wide energy range. In this paper, a neutronics analysis code system for the hybrid reactor, named NAPTH, is developed based on the conventional two-step calculation scheme widely used in the design of fission reactor. The lattice calculations are carried out by DRAGON4, and the core calculations are executed by multigroup function of MCNP. The validation results show that the results of IAEA-ADS benchmark have good agreement with results from other countries; and as for the pressure tube type hybrid reactor calculations, the code system is proven reliable and exhibits good calculation efficiency. The code system is suitable for the pressure tube type hybrid reactor calculations.