Neutron data field in a fission reactor core with fusion neutron source at pulse-periodic operation; Journal of Physics: Conference Series; Vol. 1647 : Plasma Physics and Controlled Fusion

Neutron data field in a fission reactor core with fusion neutron source at pulse-periodic operation; Journal of Physics: Conference Series; Vol. 1647 : Plasma Physics and Controlled Fusion

Бібліографічні деталі
Parent link:	Journal of Physics: Conference Series Vol. 1647 : Plasma Physics and Controlled Fusion.— 2020.— [012007, 6 p.]
Співавтори:	Национальный исследовательский Томский политехнический университет Инженерная школа ядерных технологий Научная лаборатория изотопного анализа и технологий, Национальный исследовательский Томский политехнический университет Инженерная школа ядерных технологий Отделение ядерно-топливного цикла
Інші автори:	Shamanin I. V. Igor Vladimirovich, Shmakov V. M. Vladimir Mikhaylovich, Modestov D. G. Dmitry Gennadjevich, Bedenko S. V. Sergey Vladimirovich, Polozkov S. D. Sergey Dmitrievich, Prikhodko V. V. Vadim Vadimovich, Arzhannikov A. V. Andrey Vasilyevich
Резюме:	Title screen Results are presented on the distinctive features of the energy release dynamics in the hybrid thorium reactor operating in combination with the neutron source based on the extended magnetic mirror trap. In the reactor core configuration under study, the high-temperature plasma column is formed in a pulse-periodic mode. At a certain duty cycle (pulse ratio) of the plasma column formation, it can be expected that the fission "wave" will be formed diverging from the axial region of the system and propagating in the radial direction in the fuel assembly (blanket). Under such conditions, in order to correct the resulting offset of the energy release distribution, it is necessary to optimize the fuel composition of the assembly in order to obtain the most appropriate radial distributions of physical parameters. The studies are carried out on the basis of the full-scale model of the reactor core, in which the axial region is modified: the extended magnetic mirror trap operating as a source of fusion neutrons is installed in the reactor core axial region.
Мова:	Англійська
Опубліковано:	2020
Предмети:	электронный ресурс труды учёных ТПУ
Онлайн доступ:	http://earchive.tpu.ru/handle/11683/64898 https://doi.org/10.1088/1742-6596/1647/1/012007
Формат:	Електронний ресурс Частина з книги
KOHA link:	https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=663281

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