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

Result code in IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21730%2F24%3A00381171" target="_blank" >RIV/68407700:21730/24:00381171 - isvavai.cz</a>

Alternative codes found

RIV/49777513:23220/24:43973886

Result on the web

<a href="https://doi.org/10.1115/ICONE31-133182" target="_blank" >https://doi.org/10.1115/ICONE31-133182</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1115/ICONE31-133182" target="_blank" >10.1115/ICONE31-133182</a>

Result language

angličtina

Original language name

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

Original language description

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.

Czech name

—

Czech description

—

Type

D - Article in proceedings

CEP classification

—

OECD FORD branch

20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Project

<a href="/en/project/TN02000012" target="_blank" >TN02000012: Center of Advanced Nuclear Technology II</a><br>

Continuities

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Publication year

2024

Confidentiality

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Article name in the collection

Proceedings of 31st International Conference on Nuclear Engineering

ISBN

978-0-7918-8822-3

ISSN

—

e-ISSN

—

Number of pages

8

Pages from-to

—

Publisher name

American Society of Mechanical Engineers - ASME

Place of publication

New York

Event location

Praha

Event date

Aug 4, 2024

Type of event by nationality

WRD - Celosvětová akce

UT code for WoS article

001349536700013