Analysis of Power Mesh Tally Resolution for Coupled Neutronic and Thermohydraulic Simulations of Advanced PWR Core

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21730%2F24%3A00381192" target="_blank" >RIV/68407700:21730/24:00381192 - isvavai.cz</a>

Výsledek na webu

<a href="https://www.djs.si/nene2024proceedings/pdf/NENE2024_114.pdf" target="_blank" >https://www.djs.si/nene2024proceedings/pdf/NENE2024_114.pdf</a>

DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Analysis of Power Mesh Tally Resolution for Coupled Neutronic and Thermohydraulic Simulations of Advanced PWR Core

Popis výsledku v původním jazyce

Coupled neutron transport and thermal-hydraulics calculations are essential in designing advanced nuclear reactors. The increase in computational power in recent decades has fostered research in applying high-fidelity codes to investigate reactor cores. Data Exchange between coupled codes plays a significant role in the accuracy and convergence of coupled calculations. The present study focuses on analyses of power mesh tally resolution in Monte Carlo neutron transport simulation and its corresponding influence on fuel rod temperature distribution obtained from CFD calculation. A coarse mesh tally resolution requires a smaller number of simulated neutron histories; however, it leads to a coarse resolution of the power profile in the fuel, which influences the predicted temperature field. Neutron transport simulations are performed in Monte Carlo code Serpent, and CFD calculations are performed using the open-source software OpenFOAM. The influence of power mesh tally resolution is investigated on the 3D full-core simulation of the AP1000 Pressurized Water Reactor, where two fuel assemblies were selected for the power mesh tally analysis. Further, the study includes an analysis of power distribution uncertainty in the selected fuel assemblies.

Název v anglickém jazyce

Analysis of Power Mesh Tally Resolution for Coupled Neutronic and Thermohydraulic Simulations of Advanced PWR Core

Popis výsledku anglicky

Coupled neutron transport and thermal-hydraulics calculations are essential in designing advanced nuclear reactors. The increase in computational power in recent decades has fostered research in applying high-fidelity codes to investigate reactor cores. Data Exchange between coupled codes plays a significant role in the accuracy and convergence of coupled calculations. The present study focuses on analyses of power mesh tally resolution in Monte Carlo neutron transport simulation and its corresponding influence on fuel rod temperature distribution obtained from CFD calculation. A coarse mesh tally resolution requires a smaller number of simulated neutron histories; however, it leads to a coarse resolution of the power profile in the fuel, which influences the predicted temperature field. Neutron transport simulations are performed in Monte Carlo code Serpent, and CFD calculations are performed using the open-source software OpenFOAM. The influence of power mesh tally resolution is investigated on the 3D full-core simulation of the AP1000 Pressurized Water Reactor, where two fuel assemblies were selected for the power mesh tally analysis. Further, the study includes an analysis of power distribution uncertainty in the selected fuel assemblies.

Druh

D - Stať ve sborníku

CEP obor

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OECD FORD obor

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

Projekt

<a href="/cs/project/TN02000012" target="_blank" >TN02000012: Centrum pokročilých jaderných technologií II</a><br>

Návaznosti

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

Rok uplatnění

2024

Kód důvěrnosti údajů

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

Název statě ve sborníku

Proceedings of 33rd International Conference Nuclear Energy for New Europe

ISBN

978-961-6207-59-1

ISSN

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e-ISSN

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Počet stran výsledku

8

Strana od-do

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Název nakladatele

Nuclear Society of Slovenia

Místo vydání

Ljubljana

Místo konání akce

Portorož

Datum konání akce

9. 9. 2024

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

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