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

Result code in 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>

Result on the web

<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>

Result language

angličtina

Original language name

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

Original language description

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.

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

Result was created during the realization of more than one project. More information in the Projects tab.

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

978-0-7918-8831-5

ISSN

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e-ISSN

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Number of pages

10

Pages from-to

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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

001349527900073