Gas-cooled thorium reactor at various fuel loadings and its modification by a plasma source of extra neutrons; Nuclear Science and Techniques; Vol. 30, iss. 12
| Parent link: | Nuclear Science and Techniques Vol. 30, iss. 12.— 2019.— [181, 11 p.] |
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| Corporate Authors: | , , |
| Outros autores: | , , , , , |
| Summary: | Title screen This work presents the results of computer simulation of neutronic processes in a high-temperature gas-cooled thorium reactor for 30 different options of core loading. To guarantee stable and long-term reactor operation (7–10 years), the quantity of fuel compact dispersion phase and starting fuel composition was selected. It is demonstrated that it is possible in principle to substitute the near-axial recirculation zone of the reactor core by a long magnetic trap with a high-temperature plasma column for generating thermonuclear neutrons. The distribution of neutron yield along the length of the plasma source is also presented. Such a thorium reactor, with a near-axial source of extra neutrons, can be applied for researching thermophysical and neutronic characteristics of dispersion thorium fuel to improve its properties. The results of the work are of great interest from the perspective of future advancement of the thermonuclear power industry, by means of creation of a hybrid installation based on a thorium reactor with a long plasma column as a source of additional neutrons. Режим доступа: по договору с организацией-держателем ресурса |
| Idioma: | inglés |
| Publicado: |
2019
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| Subjects: | |
| Acceso en liña: | https://doi.org/10.1007/s41365-019-0707-y |
| Formato: | Electrónico Capítulo de libro |
| KOHA link: | https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=661343 |
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| 200 | 1 | |a Gas-cooled thorium reactor at various fuel loadings and its modification by a plasma source of extra neutrons |f A. V. Arzhannikov [et al.] | |
| 203 | |a Text |c electronic | ||
| 300 | |a Title screen | ||
| 320 | |a [References: 31 tit.] | ||
| 330 | |a This work presents the results of computer simulation of neutronic processes in a high-temperature gas-cooled thorium reactor for 30 different options of core loading. To guarantee stable and long-term reactor operation (7–10 years), the quantity of fuel compact dispersion phase and starting fuel composition was selected. It is demonstrated that it is possible in principle to substitute the near-axial recirculation zone of the reactor core by a long magnetic trap with a high-temperature plasma column for generating thermonuclear neutrons. The distribution of neutron yield along the length of the plasma source is also presented. Such a thorium reactor, with a near-axial source of extra neutrons, can be applied for researching thermophysical and neutronic characteristics of dispersion thorium fuel to improve its properties. The results of the work are of great interest from the perspective of future advancement of the thermonuclear power industry, by means of creation of a hybrid installation based on a thorium reactor with a long plasma column as a source of additional neutrons. | ||
| 333 | |a Режим доступа: по договору с организацией-держателем ресурса | ||
| 461 | |t Nuclear Science and Techniques | ||
| 463 | |t Vol. 30, iss. 12 |v [181, 11 p.] |d 2019 | ||
| 610 | 1 | |a электронный ресурс | |
| 610 | 1 | |a труды учёных ТПУ | |
| 610 | 1 | |a low-power thorium reactor | |
| 610 | 1 | |a thorium hybrid reactor | |
| 610 | 1 | |a nuclear fuel evolution | |
| 610 | 1 | |a ториевые реакторы | |
| 610 | 1 | |a малые мощности | |
| 610 | 1 | |a гибридные реакторы | |
| 610 | 1 | |a эволюция | |
| 610 | 1 | |a ядерное топливо | |
| 701 | 1 | |a Arzhannikov |b A. V. |g Andrey Vasilyevich | |
| 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 Shmakov |b V. M. |g Vladimir Mikhaylovich | |
| 701 | 1 | |a Knyshev |b V. V. |c physicist |c engineer-researcher of Tomsk Polytechnic University |f 1993- |g Vladimir Vladimirovich |3 (RuTPU)RU\TPU\pers\37379 |9 20297 | |
| 701 | 1 | |a Lutsik |b I. O. |g Igor Olegovich | |
| 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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