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

Dades bibliogràfiques
Parent link:	Nuclear Science and Techniques Vol. 30, iss. 12.— 2019.— [181, 11 p.]
Autor corporatiu:	Национальный исследовательский Томский политехнический университет Инженерная школа ядерных технологий Отделение ядерно-топливного цикла, Национальный исследовательский Томский политехнический университет Школа базовой инженерной подготовки Отделение естественных наук, Национальный исследовательский Томский политехнический университет Инженерная школа ядерных технологий Научная лаборатория изотопного анализа и технологий
Altres autors:	Arzhannikov A. V. Andrey Vasilyevich, Bedenko S. V. Sergey Vladimirovich, Shmakov V. M. Vladimir Mikhaylovich, Knyshev V. V. Vladimir Vladimirovich, Lutsik I. O. Igor Olegovich, Shamanin I. V. Igor Vladimirovich
Sumari:	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:	anglès
Publicat:	2019
Matèries:	электронный ресурс труды учёных ТПУ low-power thorium reactor thorium hybrid reactor nuclear fuel evolution ториевые реакторы малые мощности гибридные реакторы эволюция ядерное топливо
Accés en línia:	https://doi.org/10.1007/s41365-019-0707-y
Format:	Electrònic Capítol de llibre
KOHA link:	https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=661343