A complementary study on the thermophysical and gas-dynamic characteristics of a hybrid fusion-fission reactor facility during operation; Nuclear Engineering and Design; Vol. 399

Chi tiết về thư mục
Parent link:Nuclear Engineering and Design
Vol. 399.— 2022.— [112037, 8 p.]
Tác giả của công ty: Национальный исследовательский Томский политехнический университет Инженерная школа ядерных технологий Отделение ядерно-топливного цикла
Tác giả khác: Arzhannikov A. V. Andrey Vasilyevich, Bedenko S. V. Sergey Vladimirovich, Prikhodko V. V. Vadim Vadimovich, Shmakov V. M. Vladimir Mikhaylovich, Modestov D. G. Dmitry Gennadjevich, Dolmatov D. O. Dmitry Olegovich, Vega-Carrillo H. R. Hector Rene
Tóm tắt:Title screen
A hybrid fusion-fission facility, which features an asymmetric assembly of fuel blocks placed in a high-temperature gas-cooled reactor and an extended plasma source of deuterium-tritium (D-T) neutrons, is investigated to evaluate its thermophysical and gas-dynamic characteristics. The proposed installation generates a power in the ∼10-100 MWth range, has small dimensions, and produces a relatively low level of radioactive waste. Thus, it is suitable for regional energy production. An optimization of the thermophysical and gas-dynamic characteristics is presented. The objective is to reduce the emerging offsets of the radial energy formed in the volume of the multiplying part of the facility. These offsets are caused by the pulsed operation of the D-T neutron plasma source.
Режим доступа: по договору с организацией-держателем ресурса
Ngôn ngữ:Tiếng Anh
Được phát hành: 2022
Những chủ đề:
Truy cập trực tuyến:https://doi.org/10.1016/j.nucengdes.2022.112037
Định dạng: Điện tử Chương của sách
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=668426
Miêu tả
Tóm tắt:Title screen
A hybrid fusion-fission facility, which features an asymmetric assembly of fuel blocks placed in a high-temperature gas-cooled reactor and an extended plasma source of deuterium-tritium (D-T) neutrons, is investigated to evaluate its thermophysical and gas-dynamic characteristics. The proposed installation generates a power in the ∼10-100 MWth range, has small dimensions, and produces a relatively low level of radioactive waste. Thus, it is suitable for regional energy production. An optimization of the thermophysical and gas-dynamic characteristics is presented. The objective is to reduce the emerging offsets of the radial energy formed in the volume of the multiplying part of the facility. These offsets are caused by the pulsed operation of the D-T neutron plasma source.
Режим доступа: по договору с организацией-держателем ресурса
DOI:10.1016/j.nucengdes.2022.112037