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

Result code in 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>

Result on the web

<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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Result language

angličtina

Original language name

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

Original language description

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.

Czech name

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Czech description

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Type

D - Article in proceedings

CEP classification

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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 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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Number of pages

8

Pages from-to

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Publisher name

Nuclear Society of Slovenia

Place of publication

Ljubljana

Event location

Portorož

Event date

Sep 9, 2024

Type of event by nationality

WRD - Celosvětová akce

UT code for WoS article

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