Development and Initial Analysis of a Neutron Diffusion Model for TEPLATOR Using COMSOL Multiphysics Software
Abstract The growing demand for sustainable energy solutions has stimulated the advancement of novel reactor technologies like TEPLATOR, a small modular reactor conceptualized by a collaborative team of researchers from the University of West Bohemia (UWB) and Czech Technical University (CTU). TEPLATOR utilizes a heavy water-cooled and moderated pressure channel-type system, providing a viable alternative to fossil fuel-based plants for industrial and district heating requirements. This assists in minimizing pollution and mitigating environmental consequences. This article covers the initial stages of developing a neutron diffusion model for the TEPLATOR core using COMSOL, a finite element-based multi-physics software package. The study focuses on creating and analyzing two- and three-dimensional diffusion models to understand spatial neutronic behavior and determine integral reactivity worth under various control rod positions. Monte Carlo-based neutron transport code Serpent is employed to compute neutronic parameters, incorporating the integration of multi-group constants into the diffusion model. Steady-state calculations for the Beginning-of-Cycle condition (BOC) are emphasized, with a comparison between computed values from the COMSOL diffusion model and Serpent simulations, along with the presentation of neutron flux distribution profiles.
Authors
- Radek Škoda (ORCID: https://orcid.org/0000-0002-8409-2349)
- Dipanjan Ray (ORCID: https://orcid.org/0000-0003-2507-7074)
- Jiří Závorka (ORCID: https://orcid.org/0000-0003-3794-2010)
- Martin Lovecký (ORCID: https://orcid.org/0000-0001-8140-3060)
Institutions
- Czech Technical University in Prague (CZ)
- University of West Bohemia in Pilsen (CZ)
Publication Details
- Published
- 2024-08-04
- DOI
- https://doi.org/10.1115/icone31-133182
- Primary Topic
- Nuclear reactor physics and engineering
- Type
- article
- Field-Weighted Citation Impact
- 0.00