Development and Initial Analysis of a Neutron Diffusion Model for TEPLATOR Using COMSOL Multiphysics Software

dc.contributor.authorRay, Dipanjan
dc.contributor.authorLovecký, Martin
dc.contributor.authorZávorka, Jiří
dc.contributor.authorŠkoda, Radek
dc.date.accessioned2025-06-20T08:36:19Z
dc.date.available2025-06-20T08:36:19Z
dc.date.issued2024
dc.date.updated2025-06-20T08:36:19Z
dc.description.abstractThe 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.format7
dc.identifier.document-number001349536700013
dc.identifier.doi10.1115/ICONE31-133182
dc.identifier.isbn978-0-7918-8822-3
dc.identifier.obd43944887
dc.identifier.orcidRay, Dipanjan 0000-0003-2507-7074
dc.identifier.orcidLovecký, Martin 0000-0001-8140-3060
dc.identifier.orcidZávorka, Jiří 0000-0003-3794-2010
dc.identifier.urihttp://hdl.handle.net/11025/60370
dc.language.isoen
dc.project.IDTN02000012
dc.publisherAmerican Society of Mechanical Engineers (ASME)
dc.relation.ispartofseries2024 31st International Conference on Nuclear Engineering, ICONE 2024
dc.subjectteplatoren
dc.subjectneutron diffusion modelen
dc.subjectCOMSOLen
dc.subjectPDEsen
dc.subjectintegral reactivity worthen
dc.titleDevelopment and Initial Analysis of a Neutron Diffusion Model for TEPLATOR Using COMSOL Multiphysics Softwareen
dc.typeStať ve sborníku (D)
dc.typeSTAŤ VE SBORNÍKU
dc.type.statusPublished Version
local.files.count1*
local.files.size1643511*
local.has.filesyes*
local.identifier.eid2-s2.0-85209079950

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