Neutronic properties of high-temperature gas-cooled reactors with thorium fuel
| Источник: | Annals of Nuclear Energy Vol. 113.— 2018.— [P. 286–293] |
|---|---|
| Автор-организация: | |
| Другие авторы: | , , , , , |
| Примечания: | Title screen High-temperature gas-cooled low-power thorium reactor units (RU) serve as ideal sources of heat energy for supply to remote areas, large naval bases and military garrisons. This study is focused on neutronic characteristics of a 60-MWth low-power thorium reactor core with fuel blocks and pellets of different configurations. The optimal configuration was selected from these combinations and enabled the reactor to operate for a minimum of 3000?days at a capacity of 60?MWth. Additionally, this study investigated the use of burnable absorber ZrB2 sprayed onto the lateral surface of the fuel pellets in the reactor to reduce the initial excess reactivity. Режим доступа: по договору с организацией-держателем ресурса |
| Язык: | английский |
| Опубликовано: |
2018
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| Предметы: | |
| Online-ссылка: | http://dx.doi.org/10.1016/j.anucene.2017.11.045 |
| Формат: | Электронный ресурс Статья |
| Запись в KOHA: | https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=657253 |
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| 200 | 1 | |a Neutronic properties of high-temperature gas-cooled reactors with thorium fuel |f I. V. Shamanin [et al.] | |
| 203 | |a Text |c electronic | ||
| 300 | |a Title screen | ||
| 320 | |a [References: 37 tit.] | ||
| 330 | |a High-temperature gas-cooled low-power thorium reactor units (RU) serve as ideal sources of heat energy for supply to remote areas, large naval bases and military garrisons. This study is focused on neutronic characteristics of a 60-MWth low-power thorium reactor core with fuel blocks and pellets of different configurations. The optimal configuration was selected from these combinations and enabled the reactor to operate for a minimum of 3000?days at a capacity of 60?MWth. Additionally, this study investigated the use of burnable absorber ZrB2 sprayed onto the lateral surface of the fuel pellets in the reactor to reduce the initial excess reactivity. | ||
| 333 | |a Режим доступа: по договору с организацией-держателем ресурса | ||
| 461 | |t Annals of Nuclear Energy | ||
| 463 | |t Vol. 113 |v [P. 286–293] |d 2018 | ||
| 610 | 1 | |a электронный ресурс | |
| 610 | 1 | |a труды учёных ТПУ | |
| 610 | 1 | |a ториевые реакторы | |
| 610 | 1 | |a сердечники | |
| 610 | 1 | |a ядро | |
| 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 | |
| 701 | 1 | |a Grachev |b V. M. |g Viktor Mikhaylovich | |
| 701 | 1 | |a Chertkov |b Yu. B. |c physicist |c Associate Professor of Tomsk Polytechnic University, Candidate of physical and mathematical sciences |f 1948- |g Yuri Borisovich |3 (RuTPU)RU\TPU\pers\31212 |9 15408 | |
| 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 Mendoza |b O. |g Quiroz Orlando Jose | |
| 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 | |
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