Neutronic Modelling and Computation of TEPLATOR Core using COMSOL Multiphysics Code

Abstract

TEPLATOR is an innovative heavy water small modular reactor concept that has the potential to meet district and industrial heating demands by harnessing nuclear energy as a heat source. This approach offers a substantial reduction in pollution and environmental impact compared to conventional heating methods reliant on fossil fuels.The primary objective of this article is to develop a two-dimensional, multi-group neutron diffusion model for the TEPLATOR reactor core using the COMSOL Multiphysics software package. COMSOL code employs a finite element numerical scheme to solve the partial differential equations associated with the neutron diffusion model. Monte Carlo transport code Serpent version 2.2.1 with the latest ENDF/B-VIII.0 nuclear data library is employed to calculate the multi-group constants for different reactor regions. These multi-group constants are then incorporated in the developed COMSOL neutron diffusion model to perform calculations using adaptive mesh refinement technique to enhance the accuracy of the solution. Neutronic behaviour of the TEPLATOR reactor core is obtained by calculating the criticality of the system and analysing the steady-state neutron-flux distribution profile. The calculated results are subsequently compared with those generated by the Serpent, providing a basis for validation and further analysis.