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; Vol. 53, iss. 6
| Parent link: | Nuclear Engineering and Technology Vol. 53, iss. 6.— 2021.— [P. 1-11] |
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| 団体著者: | |
| その他の著者: | , , , , , , , |
| 要約: | Title screen 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. |
| 言語: | 英語 |
| 出版事項: |
2021
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| 主題: | |
| オンライン･アクセス: | https://doi.org/10.1016/j.net.2020.11.026 |
| フォーマット: | MixedMaterials 電子媒体 図書の章 |
| KOHA link: | https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=664799 |
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| 200 | 1 | |a Maintaining the close-to-critical state of thorium fuel core of hybrid reactor operated under control by D-T fusion neutron flux |f S. V. Bedenko, A. V. Arzhannikov, I. O. Lutsik [et al.] | |
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| 300 | |a Title screen | ||
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| 330 | |a 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. | ||
| 461 | |t Nuclear Engineering and Technology | ||
| 463 | |t Vol. 53, iss. 6 |v [P. 1-11] |d 2021 | ||
| 610 | 1 | |a электронный ресурс | |
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| 610 | 1 | |a wave fissions | |
| 610 | 1 | |a plasma pulse-periodic generator | |
| 610 | 1 | |a D-T neutrons | |
| 610 | 1 | |a hybrid fusion–fission reactor | |
| 610 | 1 | |a thorium-containing fuel | |
| 610 | 1 | |a деления | |
| 610 | 1 | |a гибридные реакторы | |
| 610 | 1 | |a торийсодержащие системы | |
| 701 | 1 | |a Bedenko |b S. V. |c physicist |c Associate Professor of Tomsk Polytechnic University, Candidate of physical and mathematical sciences |f 1980- |g Sergey Vladimirovich |3 (RuTPU)RU\TPU\pers\30831 |9 15078 | |
| 701 | 1 | |a Arzhannikov |b A. V. |g Andrey Vasilyevich | |
| 701 | 1 | |a Lutsik |b I. O. |g Igor Olegovich | |
| 701 | 1 | |a Prikhodko |b V. V. |g Vadim Vadimovich | |
| 701 | 1 | |a Shmakov |b V. N. |g Vladimir Mikhaylovich | |
| 701 | 1 | |a Modestov |b D. G. |g Dmitry Gennadjevich | |
| 701 | 1 | |a Karengin |b A. G. |c physicist |c Associate Professor of Tomsk Polytechnic University, Candidate of physical and mathematical sciences |f 1950- |g Aleksandr Grigorievich |3 (RuTPU)RU\TPU\pers\31220 |9 15415 | |
| 701 | 1 | |a Shamanin |b I. V. |c specialist in the field of nuclear physics |c Professor of Tomsk Polytechnic University, Doctor of physical and mathematical sciences |c specialist in the field of nuclear power engineering |f 1962- |g Igor Vladimirovich |3 (RuTPU)RU\TPU\pers\30832 | |
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