PRATIC: A soluble-boron-free, pressurized water cooled, SMR core benchmark

Current nuclear reactor research is actively exploring small modular pressurized water reactors (PWRs), particularly soluble-boron-free (SBF) configurations. SBF designs utilize control rods and gadolinium-poisoned fuel rods to manage reactivity. Additionally, small modular reactors (SMRs) commonly...

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Main Authors: Vuiart Romain, Eustache Aimeric, Eveillard Sarah, Prulhière Géraud
Format: Article
Language:English
Published: EDP Sciences 2024-01-01
Series:EPJ Nuclear Sciences & Technologies
Online Access:https://www.epj-n.org/articles/epjn/full_html/2024/01/epjn20240027/epjn20240027.html
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author Vuiart Romain
Eustache Aimeric
Eveillard Sarah
Prulhière Géraud
author_facet Vuiart Romain
Eustache Aimeric
Eveillard Sarah
Prulhière Géraud
author_sort Vuiart Romain
collection DOAJ
description Current nuclear reactor research is actively exploring small modular pressurized water reactors (PWRs), particularly soluble-boron-free (SBF) configurations. SBF designs utilize control rods and gadolinium-poisoned fuel rods to manage reactivity. Additionally, small modular reactors (SMRs) commonly integrate steel reflectors to minimize neutron leakage. However, the compactness of SMRs and the adoption of these technical solutions result in notable fluctuations in neutron flux within the core during normal cycle operation. Hence, comprehensive analysis is essential, especially concerning reactor performance under normal and accident conditions, the reliability of neutronics calculation assumptions, etc. Research into these issues requires reactor core neutronics benchmarks that are consistent with industrial concepts so that the analysis results can be applied to real reactors. In this context, this article introduces PRATIC, a SBF-PWR SMR core neutronics benchmark designed to match the global performances of industrial concepts. The development of PRATIC was conducted using a deterministic calculation scheme coupling the APOLLO2 and CRONOS2 codes. PRATIC features a thermal power of 350 MWth, an equilibrium cycle length of 1.9 years, and an average discharge burnup of about 34 GWd/t, while maintaining controlled power distributions. The article elaborates on the design assumptions for PRATIC, then details the reactor core and its equilibrium cycle. Access to the PRATIC modeling data is available via a GIT repository, accessible upon request via email at pratic@cea.fr.
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issn 2491-9292
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publishDate 2024-01-01
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series EPJ Nuclear Sciences & Technologies
spelling doaj-art-d5179ef5e39f4e67b2da05fd86f9985b2025-01-06T11:33:52ZengEDP SciencesEPJ Nuclear Sciences & Technologies2491-92922024-01-01102510.1051/epjn/2024026epjn20240027PRATIC: A soluble-boron-free, pressurized water cooled, SMR core benchmarkVuiart Romain0https://orcid.org/0000-0002-3032-348XEustache Aimeric1Eveillard Sarah2Prulhière Géraud3https://orcid.org/0000-0001-6402-0447French Atomic Energy and Alternative Energy Commission (CEA), DES/IRESNE/DER/SPRC/LE2C CadaracheFrench Atomic Energy and Alternative Energy Commission (CEA), DES/IRESNE/DER/SPRC/LE2C CadaracheFrench Atomic Energy and Alternative Energy Commission (CEA), DES/IRESNE/DER/SPRC/LE2C CadaracheFrench Atomic Energy and Alternative Energy Commission (CEA), DES/IRESNE/DER/SPRC/LE2C CadaracheCurrent nuclear reactor research is actively exploring small modular pressurized water reactors (PWRs), particularly soluble-boron-free (SBF) configurations. SBF designs utilize control rods and gadolinium-poisoned fuel rods to manage reactivity. Additionally, small modular reactors (SMRs) commonly integrate steel reflectors to minimize neutron leakage. However, the compactness of SMRs and the adoption of these technical solutions result in notable fluctuations in neutron flux within the core during normal cycle operation. Hence, comprehensive analysis is essential, especially concerning reactor performance under normal and accident conditions, the reliability of neutronics calculation assumptions, etc. Research into these issues requires reactor core neutronics benchmarks that are consistent with industrial concepts so that the analysis results can be applied to real reactors. In this context, this article introduces PRATIC, a SBF-PWR SMR core neutronics benchmark designed to match the global performances of industrial concepts. The development of PRATIC was conducted using a deterministic calculation scheme coupling the APOLLO2 and CRONOS2 codes. PRATIC features a thermal power of 350 MWth, an equilibrium cycle length of 1.9 years, and an average discharge burnup of about 34 GWd/t, while maintaining controlled power distributions. The article elaborates on the design assumptions for PRATIC, then details the reactor core and its equilibrium cycle. Access to the PRATIC modeling data is available via a GIT repository, accessible upon request via email at pratic@cea.fr.https://www.epj-n.org/articles/epjn/full_html/2024/01/epjn20240027/epjn20240027.html
spellingShingle Vuiart Romain
Eustache Aimeric
Eveillard Sarah
Prulhière Géraud
PRATIC: A soluble-boron-free, pressurized water cooled, SMR core benchmark
EPJ Nuclear Sciences & Technologies
title PRATIC: A soluble-boron-free, pressurized water cooled, SMR core benchmark
title_full PRATIC: A soluble-boron-free, pressurized water cooled, SMR core benchmark
title_fullStr PRATIC: A soluble-boron-free, pressurized water cooled, SMR core benchmark
title_full_unstemmed PRATIC: A soluble-boron-free, pressurized water cooled, SMR core benchmark
title_short PRATIC: A soluble-boron-free, pressurized water cooled, SMR core benchmark
title_sort pratic a soluble boron free pressurized water cooled smr core benchmark
url https://www.epj-n.org/articles/epjn/full_html/2024/01/epjn20240027/epjn20240027.html
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AT eustacheaimeric praticasolubleboronfreepressurizedwatercooledsmrcorebenchmark
AT eveillardsarah praticasolubleboronfreepressurizedwatercooledsmrcorebenchmark
AT prulhieregeraud praticasolubleboronfreepressurizedwatercooledsmrcorebenchmark