Neutronic analysis of HPLWR fuel assembly cluster

Graphical abstract: Display Omitted Highlights: ► The neutronic analysis of fuel assembly cluster of the HPLWR is discussed in the present study. ► The computer code WIMS-D4 and CITATION were used for neutronic computation. ► The codes have jointly been used for neutronic calculation of different thermal power reactors. ► The thermal flux reaches its maximum value in the moderator channel and the assembly gap. -- Abstract: In the present study the neutronic analysis of fuel assembly cluster of the HPLWR is discussed. Neutronic calculations are performed using WIMS-D4 and CITATION codes. Thermal–hydraulic code containing the properties and specifications of the fuel assembly of HPLWR is utilized. The calculated axial power in each selected control volume is used in the thermal–hydraulic code to get the properties of the fluid and fuel needed for further neutronic analysis. The process of coupling continues until convergence is achieved. Finally, the obtained neutronic results including axial power distribution, neutron flux, and power peaking factors are discussed in the present article.