Development of core fuel management code system for CANDU reactor based on coupled neutronics and thermal-hydraulic advanced nodal method

In this paper, a fuel management program for pressurized heavy water reactor (FMPHWR) based on advanced three-dimensional nodal method has been developed, which was integrated with thermal hydraulic code to realize the coupling of neutronics and thermal-hydraulic. To generate the lattice cross sections of instantaneous state, a refined parameterized cross section method was used in FMPHWR. A modified time-averaged model was developed. It has been implemented in FMPHWR and tested with Qinshan Phase III CANDU reactor. The numerical results show that FMPHWR has superior computational efficiency and accuracy.