Overview of Fourth Generation Reactors Studied at the Universidade Federal de Minas Gerais (Brazil)
This paper presents the results of the studies about the Fourth Generation Reactors developed at DENU-UFMG, such as the Very High Temperature Reactor (VHTR), Molten Salt Breeder Reactor (MSBR), Sodium Fast Reactor (SFR) and Gas-cooled Fast Reactor (GFR). These studies evaluate neutronic parameters o...
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| Format: | Article |
| Language: | English |
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Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR)
2024-03-01
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| Series: | Brazilian Journal of Radiation Sciences |
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| Online Access: | https://bjrs.org.br/revista/index.php/REVISTA/article/view/2419 |
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| _version_ | 1849423892609761280 |
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| author | Clarysson Alberto Mello da Silva Anderson Altair Pinheiro de Macedo Maurício Gilberti Fabiano Cardoso da Silva Isabella Resende Magalhães Antonella Lombardi Costa Claubia Pereira |
| author_facet | Clarysson Alberto Mello da Silva Anderson Altair Pinheiro de Macedo Maurício Gilberti Fabiano Cardoso da Silva Isabella Resende Magalhães Antonella Lombardi Costa Claubia Pereira |
| author_sort | Clarysson Alberto Mello da Silva |
| collection | DOAJ |
| description | This paper presents the results of the studies about the Fourth Generation Reactors developed at DENU-UFMG, such as the Very High Temperature Reactor (VHTR), Molten Salt Breeder Reactor (MSBR), Sodium Fast Reactor (SFR) and Gas-cooled Fast Reactor (GFR). These studies evaluate neutronic parameters of the nuclear system at steady state and during the burnup using computer models developed at DENU-UFMG using SCALE 6.0 (KENO-VI/ORIGENS), MCNPX 2.6.0 and MCNP5. The results show that the adopted methodologies confirm the capabilities of the codes to simulate specific situations in steady state or transient operating conditions. |
| format | Article |
| id | doaj-art-7ef70fa18a4c41b1bd9de393fca49be9 |
| institution | Kabale University |
| issn | 2319-0612 |
| language | English |
| publishDate | 2024-03-01 |
| publisher | Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR) |
| record_format | Article |
| series | Brazilian Journal of Radiation Sciences |
| spelling | doaj-art-7ef70fa18a4c41b1bd9de393fca49be92025-08-20T03:30:25ZengBrazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR)Brazilian Journal of Radiation Sciences2319-06122024-03-01121e2419e241910.15392/2319-0612.2024.24192042Overview of Fourth Generation Reactors Studied at the Universidade Federal de Minas Gerais (Brazil)Clarysson Alberto Mello da Silva0Anderson Altair Pinheiro de Macedo1Maurício Gilberti2Fabiano Cardoso da Silva3Isabella Resende Magalhães4Antonella Lombardi Costa5Claubia Pereira6Federal University of Minas GeraisFederal University of Minas GeraisFederal University of Minas GeraisFederal University of Minas GeraisFederal University of Minas GeraisFederal University of Minas GeraisFederal University of Minas GeraisThis paper presents the results of the studies about the Fourth Generation Reactors developed at DENU-UFMG, such as the Very High Temperature Reactor (VHTR), Molten Salt Breeder Reactor (MSBR), Sodium Fast Reactor (SFR) and Gas-cooled Fast Reactor (GFR). These studies evaluate neutronic parameters of the nuclear system at steady state and during the burnup using computer models developed at DENU-UFMG using SCALE 6.0 (KENO-VI/ORIGENS), MCNPX 2.6.0 and MCNP5. The results show that the adopted methodologies confirm the capabilities of the codes to simulate specific situations in steady state or transient operating conditions.https://bjrs.org.br/revista/index.php/REVISTA/article/view/2419generation four nuclear reactorsnuclear fuel cycleneutronic simulations |
| spellingShingle | Clarysson Alberto Mello da Silva Anderson Altair Pinheiro de Macedo Maurício Gilberti Fabiano Cardoso da Silva Isabella Resende Magalhães Antonella Lombardi Costa Claubia Pereira Overview of Fourth Generation Reactors Studied at the Universidade Federal de Minas Gerais (Brazil) Brazilian Journal of Radiation Sciences generation four nuclear reactors nuclear fuel cycle neutronic simulations |
| title | Overview of Fourth Generation Reactors Studied at the Universidade Federal de Minas Gerais (Brazil) |
| title_full | Overview of Fourth Generation Reactors Studied at the Universidade Federal de Minas Gerais (Brazil) |
| title_fullStr | Overview of Fourth Generation Reactors Studied at the Universidade Federal de Minas Gerais (Brazil) |
| title_full_unstemmed | Overview of Fourth Generation Reactors Studied at the Universidade Federal de Minas Gerais (Brazil) |
| title_short | Overview of Fourth Generation Reactors Studied at the Universidade Federal de Minas Gerais (Brazil) |
| title_sort | overview of fourth generation reactors studied at the universidade federal de minas gerais brazil |
| topic | generation four nuclear reactors nuclear fuel cycle neutronic simulations |
| url | https://bjrs.org.br/revista/index.php/REVISTA/article/view/2419 |
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