Neutronic Modelling and Computation of TEPLATOR Core using COMSOL Multiphysics Code

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F49777513%3A23220%2F23%3A43970609" target="_blank" >RIV/49777513:23220/23:43970609 - isvavai.cz</a>

Výsledek na webu

<a href="https://www.djs.si/upload/nene/2023/proceedings/Contribution_926_final.pdf" target="_blank" >https://www.djs.si/upload/nene/2023/proceedings/Contribution_926_final.pdf</a>

DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Neutronic Modelling and Computation of TEPLATOR Core using COMSOL Multiphysics Code

Popis výsledku v původním jazyce

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.

Název v anglickém jazyce

Neutronic Modelling and Computation of TEPLATOR Core using COMSOL Multiphysics Code

Popis výsledku anglicky

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.

Druh

O - Ostatní výsledky

CEP obor

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OECD FORD obor

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

Projekt

<a href="/cs/project/TK02030069" target="_blank" >TK02030069: Energy Storage při produkci elektřiny</a><br>

Návaznosti

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

Rok uplatnění

2023

Kód důvěrnosti údajů

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