Analysis of Operational Characteristics of a Small Modular Reactor With Accident Tolerant Fuel

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F24%3A00381356" target="_blank" >RIV/68407700:21340/24:00381356 - isvavai.cz</a>

Výsledek na webu

<a href="https://doi.org/10.1115/ICONE31-136104" target="_blank" >https://doi.org/10.1115/ICONE31-136104</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1115/ICONE31-136104" target="_blank" >10.1115/ICONE31-136104</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Analysis of Operational Characteristics of a Small Modular Reactor With Accident Tolerant Fuel

Popis výsledku v původním jazyce

The topic of the paper is focused on numerical simulations of nuclear reactors, the preparation of macroscopic nuclear data using a deterministic approach, and the analysis (with an optimisation proposal) of selected Accident Tolerant Fuel (ATF) concepts of fuel pellets. The behaviour of ATFs in large cores has already been investigated in depth, but analyses in small cores have not yet been studied in more detail. Macroscopic nuclear data were prepared using the SCALE-Triton computational code on an infinite fuel assembly model. Subsequently, a 3D full-core calculation is performed in the deterministic macrocode PARCS on the model of a light-water Small Modular Reactor (SMR) developed by the NuScale Power company. For proper interpretation of results, coupling of PARCS with an external thermohydraulic solver PATHS, is studied. The behaviour of selected ATFs and deviations of various neutronic parameters from the referenced UO2 fuel are analysed in this complex model. Together with the analyses, a proposal on the optimisation of the referenced core with the (U10Mo/UN/ThO2) pellets combination for the use on this model, is presented. This optimisation proposal brought the possibility of extending the fuel campaign (while maintaining the same average fuel enrichment), reducing the average fuel temperature and improving the inherent safety parameters, at the expense of a slight increase in the value of the maximum peaking factors.

Název v anglickém jazyce

Analysis of Operational Characteristics of a Small Modular Reactor With Accident Tolerant Fuel

Popis výsledku anglicky

The topic of the paper is focused on numerical simulations of nuclear reactors, the preparation of macroscopic nuclear data using a deterministic approach, and the analysis (with an optimisation proposal) of selected Accident Tolerant Fuel (ATF) concepts of fuel pellets. The behaviour of ATFs in large cores has already been investigated in depth, but analyses in small cores have not yet been studied in more detail. Macroscopic nuclear data were prepared using the SCALE-Triton computational code on an infinite fuel assembly model. Subsequently, a 3D full-core calculation is performed in the deterministic macrocode PARCS on the model of a light-water Small Modular Reactor (SMR) developed by the NuScale Power company. For proper interpretation of results, coupling of PARCS with an external thermohydraulic solver PATHS, is studied. The behaviour of selected ATFs and deviations of various neutronic parameters from the referenced UO2 fuel are analysed in this complex model. Together with the analyses, a proposal on the optimisation of the referenced core with the (U10Mo/UN/ThO2) pellets combination for the use on this model, is presented. This optimisation proposal brought the possibility of extending the fuel campaign (while maintaining the same average fuel enrichment), reducing the average fuel temperature and improving the inherent safety parameters, at the expense of a slight increase in the value of the maximum peaking factors.

Druh

D - Stať ve sborníku

CEP obor

—

OECD FORD obor

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

Projekt

Výsledek vznikl pri realizaci vícero projektů. Více informací v záložce Projekty.

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 31st International Conference on Nuclear Engineering

ISBN

978-0-7918-8831-5

ISSN

—

e-ISSN

—

Počet stran výsledku

10

Strana od-do

—

Název nakladatele

American Society of Mechanical Engineers - ASME

Místo vydání

New York

Místo konání akce

Praha

Datum konání akce

4. 8. 2024

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

001349527900073