Small Modular Reactor based on NuScale with Thorium base

This study proposes a novel approach to enhance the NuScale Small Modular Reactor (SMR) by incorporating mixed uranium-thorium (U-Th) oxide fuel, thereby increasing U-233 production, improving fuel use, and reducing radioactive waste. The research integrates advanced neutron transport simulations w...

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Main Authors: Diego M. E. Gonçalves, Marcelo Vilela da Silva, C. J. C. M. R. da Cunha, Giovanni L. Stefani
Format: Article
Language:English
Published: Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR) 2025-07-01
Series:Brazilian Journal of Radiation Sciences
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Online Access:https://bjrs.org.br/revista/index.php/REVISTA/article/view/2881
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author Diego M. E. Gonçalves
Marcelo Vilela da Silva
C. J. C. M. R. da Cunha
Giovanni L. Stefani
author_facet Diego M. E. Gonçalves
Marcelo Vilela da Silva
C. J. C. M. R. da Cunha
Giovanni L. Stefani
author_sort Diego M. E. Gonçalves
collection DOAJ
description This study proposes a novel approach to enhance the NuScale Small Modular Reactor (SMR) by incorporating mixed uranium-thorium (U-Th) oxide fuel, thereby increasing U-233 production, improving fuel use, and reducing radioactive waste. The research integrates advanced neutron transport simulations with optimization techniques to refine the reactor’s fuel design for greater sustainability and efficiency. The researchers modeled the reference NuScale reactor core using the SERPENT code, which relies on the Monte Carlo Method (MCM) to ensure exact neutron transport simulations. To meet substantial computational demands, they ran these simulations on the Lobo Carneiro supercomputer at NACAD/UFRJ. The team applied a Particle Swarm Optimization (PSO) algorithm to find the best seed-to-blanket volume ratio, thereby maximizing U-233 production and achieving a self-sustaining fuel cycle. Implemented in Python, the algorithm continuously adjusted reactor parameters, logged progress, and enabled ongoing monitoring and potential restarts. For the seed region, the researchers employed a 13x13 configuration and used a 19x19 configuration for the blanket. They evaluated the proposed core design against critical safety and performance metrics, including the Moderator Temperature Coefficient (MTC), Doppler Temperature Coefficient (DTC), boron worth coefficient (BWC). The team also conducted data analysis and visualization using SerpentTools in Python. The results show that integrating U-Th fuel into SMRs can boost reactor performance without compromising safety, thereby offering a promising path toward more sustainable, efficient, and scalable nuclear energy production. This approach can reshape next-generation nuclear reactors by addressing essential challenges related to fuel sustainability and waste management.
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issn 2319-0612
language English
publishDate 2025-07-01
publisher Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR)
record_format Article
series Brazilian Journal of Radiation Sciences
spelling doaj-art-d0c274e05f854680903b8f6015c7d4fe2025-08-20T03:28:18ZengBrazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR)Brazilian Journal of Radiation Sciences2319-06122025-07-01132A (Suppl.)10.15392/2319-0612.2025.28812506Small Modular Reactor based on NuScale with Thorium baseDiego M. E. Gonçalves0Marcelo Vilela da Silva1C. J. C. M. R. da Cunha2Giovanni L. Stefani3a Nuclear Engineering Program / Universidade Federal do Rio de Janeiro / COPPE, Av. Horácio Macedo, 2030, Bloco G - Sala 206 - CT, University City, Rio de Janeiro, RJ, Brazila Nuclear Engineering Program / Universidade Federal do Rio de Janeiro / COPPE, Av. Horácio Macedo, 2030, Bloco G - Sala 206 - CT, University City, Rio de Janeiro, RJ, Brazilb Centro Regional de Ciências Nucleares do Nordeste (CRCN-NE/CNEN), Av. Prof.Luis Freire N°200-Curado, Recife - PE, 50740-437, Brazila Nuclear Engineering Program / Universidade Federal do Rio de Janeiro / COPPE, Av. Horácio Macedo, 2030, Bloco G - Sala 206 - CT, University City, Rio de Janeiro, RJ, Brazil This study proposes a novel approach to enhance the NuScale Small Modular Reactor (SMR) by incorporating mixed uranium-thorium (U-Th) oxide fuel, thereby increasing U-233 production, improving fuel use, and reducing radioactive waste. The research integrates advanced neutron transport simulations with optimization techniques to refine the reactor’s fuel design for greater sustainability and efficiency. The researchers modeled the reference NuScale reactor core using the SERPENT code, which relies on the Monte Carlo Method (MCM) to ensure exact neutron transport simulations. To meet substantial computational demands, they ran these simulations on the Lobo Carneiro supercomputer at NACAD/UFRJ. The team applied a Particle Swarm Optimization (PSO) algorithm to find the best seed-to-blanket volume ratio, thereby maximizing U-233 production and achieving a self-sustaining fuel cycle. Implemented in Python, the algorithm continuously adjusted reactor parameters, logged progress, and enabled ongoing monitoring and potential restarts. For the seed region, the researchers employed a 13x13 configuration and used a 19x19 configuration for the blanket. They evaluated the proposed core design against critical safety and performance metrics, including the Moderator Temperature Coefficient (MTC), Doppler Temperature Coefficient (DTC), boron worth coefficient (BWC). The team also conducted data analysis and visualization using SerpentTools in Python. The results show that integrating U-Th fuel into SMRs can boost reactor performance without compromising safety, thereby offering a promising path toward more sustainable, efficient, and scalable nuclear energy production. This approach can reshape next-generation nuclear reactors by addressing essential challenges related to fuel sustainability and waste management. https://bjrs.org.br/revista/index.php/REVISTA/article/view/2881Reactor CoreFuel CycleNuScaleSMRNuclear fuel cycles
spellingShingle Diego M. E. Gonçalves
Marcelo Vilela da Silva
C. J. C. M. R. da Cunha
Giovanni L. Stefani
Small Modular Reactor based on NuScale with Thorium base
Brazilian Journal of Radiation Sciences
Reactor Core
Fuel Cycle
NuScale
SMR
Nuclear fuel cycles
title Small Modular Reactor based on NuScale with Thorium base
title_full Small Modular Reactor based on NuScale with Thorium base
title_fullStr Small Modular Reactor based on NuScale with Thorium base
title_full_unstemmed Small Modular Reactor based on NuScale with Thorium base
title_short Small Modular Reactor based on NuScale with Thorium base
title_sort small modular reactor based on nuscale with thorium base
topic Reactor Core
Fuel Cycle
NuScale
SMR
Nuclear fuel cycles
url https://bjrs.org.br/revista/index.php/REVISTA/article/view/2881
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AT marcelovileladasilva smallmodularreactorbasedonnuscalewiththoriumbase
AT cjcmrdacunha smallmodularreactorbasedonnuscalewiththoriumbase
AT giovannilstefani smallmodularreactorbasedonnuscalewiththoriumbase