Maintaining the close-to-critical state of thorium fuel core of hybrid reactor operated under control by D-T fusion neutron flux
The results of full-scale numerical experiments of a hybrid thorium-containing fuel cell facility operating in a close-to-critical state due to a controlled source of fusion neutrons are discussed in this work. The facility under study was a complex consisting of two blocks. The first block was base...
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Elsevier
2021-06-01
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| Series: | Nuclear Engineering and Technology |
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| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573320309414 |
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| author | Sergey V. Bedenko Andrey V. Arzhannikov Igor O. Lutsik Vadim V. Prikhodko Vladimir M. Shmakov Dmitry G. Modestov Alexander G. Karengin Igor V. Shamanin |
| author_facet | Sergey V. Bedenko Andrey V. Arzhannikov Igor O. Lutsik Vadim V. Prikhodko Vladimir M. Shmakov Dmitry G. Modestov Alexander G. Karengin Igor V. Shamanin |
| author_sort | Sergey V. Bedenko |
| collection | DOAJ |
| description | The results of full-scale numerical experiments of a hybrid thorium-containing fuel cell facility operating in a close-to-critical state due to a controlled source of fusion neutrons are discussed in this work. The facility under study was a complex consisting of two blocks. The first block was based on the concept of a high-temperature gas-cooled thorium reactor core. The second block was an axially symmetrical extended plasma generator of additional neutrons that was placed in the near-axial zone of the facility blanket. The calculated models of the blanket and the plasma generator of D-T neutrons created within the work allowed for research of the neutronic parameters of the facility in stationary and pulse-periodic operation modes. This research will make it possible to construct a safe facility and investigate the properties of thorium fuel, which can be continuously used in the epithermal spectrum of the considered hybrid fusion–fission reactor. |
| first_indexed | 2024-12-17T04:56:14Z |
| format | Article |
| id | doaj.art-52b1309dedac49529f43c41727a63cfd |
| institution | Directory Open Access Journal |
| issn | 1738-5733 |
| language | English |
| last_indexed | 2024-12-17T04:56:14Z |
| publishDate | 2021-06-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj.art-52b1309dedac49529f43c41727a63cfd2022-12-21T22:02:42ZengElsevierNuclear Engineering and Technology1738-57332021-06-0153617361746Maintaining the close-to-critical state of thorium fuel core of hybrid reactor operated under control by D-T fusion neutron fluxSergey V. Bedenko0Andrey V. Arzhannikov1Igor O. Lutsik2Vadim V. Prikhodko3Vladimir M. Shmakov4Dmitry G. Modestov5Alexander G. Karengin6Igor V. Shamanin7National Research Tomsk Polytechnic University, Tomsk, 634 034, Russian Federation; Corresponding author.Budker Institute of Nuclear Physics of Siberian Branch Russian Academy of Sciences, Novosibirsk, 630 090, Russian FederationNational Research Tomsk Polytechnic University, Tomsk, 634 034, Russian FederationBudker Institute of Nuclear Physics of Siberian Branch Russian Academy of Sciences, Novosibirsk, 630 090, Russian FederationFederal State Unitary Enterprise «Russian Federal Nuclear Center - Zababakhin All-Russia Research Institute of Technical Physics», 456 770, Russian FederationFederal State Unitary Enterprise «Russian Federal Nuclear Center - Zababakhin All-Russia Research Institute of Technical Physics», 456 770, Russian FederationNational Research Tomsk Polytechnic University, Tomsk, 634 034, Russian FederationNational Research Tomsk Polytechnic University, Tomsk, 634 034, Russian FederationThe results of full-scale numerical experiments of a hybrid thorium-containing fuel cell facility operating in a close-to-critical state due to a controlled source of fusion neutrons are discussed in this work. The facility under study was a complex consisting of two blocks. The first block was based on the concept of a high-temperature gas-cooled thorium reactor core. The second block was an axially symmetrical extended plasma generator of additional neutrons that was placed in the near-axial zone of the facility blanket. The calculated models of the blanket and the plasma generator of D-T neutrons created within the work allowed for research of the neutronic parameters of the facility in stationary and pulse-periodic operation modes. This research will make it possible to construct a safe facility and investigate the properties of thorium fuel, which can be continuously used in the epithermal spectrum of the considered hybrid fusion–fission reactor.http://www.sciencedirect.com/science/article/pii/S1738573320309414Wave» fissionsPlasma pulse-periodic generatorD-T neutronsHybrid fusion–fission reactorThorium-containing fuel |
| spellingShingle | Sergey V. Bedenko Andrey V. Arzhannikov Igor O. Lutsik Vadim V. Prikhodko Vladimir M. Shmakov Dmitry G. Modestov Alexander G. Karengin Igor V. Shamanin Maintaining the close-to-critical state of thorium fuel core of hybrid reactor operated under control by D-T fusion neutron flux Nuclear Engineering and Technology Wave» fissions Plasma pulse-periodic generator D-T neutrons Hybrid fusion–fission reactor Thorium-containing fuel |
| title | Maintaining the close-to-critical state of thorium fuel core of hybrid reactor operated under control by D-T fusion neutron flux |
| title_full | Maintaining the close-to-critical state of thorium fuel core of hybrid reactor operated under control by D-T fusion neutron flux |
| title_fullStr | Maintaining the close-to-critical state of thorium fuel core of hybrid reactor operated under control by D-T fusion neutron flux |
| title_full_unstemmed | Maintaining the close-to-critical state of thorium fuel core of hybrid reactor operated under control by D-T fusion neutron flux |
| title_short | Maintaining the close-to-critical state of thorium fuel core of hybrid reactor operated under control by D-T fusion neutron flux |
| title_sort | maintaining the close to critical state of thorium fuel core of hybrid reactor operated under control by d t fusion neutron flux |
| topic | Wave» fissions Plasma pulse-periodic generator D-T neutrons Hybrid fusion–fission reactor Thorium-containing fuel |
| url | http://www.sciencedirect.com/science/article/pii/S1738573320309414 |
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