Development and Initial Analysis of a Neutron Diffusion Model for TEPLATOR Using COMSOL Multiphysics Software
| dc.contributor.author | Ray, Dipanjan | |
| dc.contributor.author | Lovecký, Martin | |
| dc.contributor.author | Závorka, Jiří | |
| dc.contributor.author | Škoda, Radek | |
| dc.date.accessioned | 2025-06-20T08:36:19Z | |
| dc.date.available | 2025-06-20T08:36:19Z | |
| dc.date.issued | 2024 | |
| dc.date.updated | 2025-06-20T08:36:19Z | |
| dc.description.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. | en |
| dc.format | 7 | |
| dc.identifier.document-number | 001349536700013 | |
| dc.identifier.doi | 10.1115/ICONE31-133182 | |
| dc.identifier.isbn | 978-0-7918-8822-3 | |
| dc.identifier.obd | 43944887 | |
| dc.identifier.orcid | Ray, Dipanjan 0000-0003-2507-7074 | |
| dc.identifier.orcid | Lovecký, Martin 0000-0001-8140-3060 | |
| dc.identifier.orcid | Závorka, Jiří 0000-0003-3794-2010 | |
| dc.identifier.uri | http://hdl.handle.net/11025/60370 | |
| dc.language.iso | en | |
| dc.project.ID | TN02000012 | |
| dc.publisher | American Society of Mechanical Engineers (ASME) | |
| dc.relation.ispartofseries | 2024 31st International Conference on Nuclear Engineering, ICONE 2024 | |
| dc.subject | teplator | en |
| dc.subject | neutron diffusion model | en |
| dc.subject | COMSOL | en |
| dc.subject | PDEs | en |
| dc.subject | integral reactivity worth | en |
| dc.title | Development and Initial Analysis of a Neutron Diffusion Model for TEPLATOR Using COMSOL Multiphysics Software | en |
| dc.type | Stať ve sborníku (D) | |
| dc.type | STAŤ VE SBORNÍKU | |
| dc.type.status | Published Version | |
| local.files.count | 1 | * |
| local.files.size | 1643511 | * |
| local.has.files | yes | * |
| local.identifier.eid | 2-s2.0-85209079950 |
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