Neutronic properties of high-temperature gas-cooled reactors with thorium fuel; Annals of Nuclear Energy; Vol. 113

Neutronic properties of high-temperature gas-cooled reactors with thorium fuel; Annals of Nuclear Energy; Vol. 113

Bibliographic Details
Parent link:Annals of Nuclear Energy
Vol. 113.— 2018.— [P. 286–293]
Corporate Author: Национальный исследовательский Томский политехнический университет
Other Authors: Shamanin I. V. Igor Vladimirovich, Grachev V. M. Viktor Mikhaylovich, Chertkov Yu. B. Yuri Borisovich, Bedenko S. V. Sergey Vladimirovich, Mendoza O. Quiroz Orlando Jose, Knyshev V. V. Vladimir Vladimirovich
Summary: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
Language:English
Published: 2018
Subjects:
электронный ресурс
труды учёных ТПУ
ториевые реакторы
сердечники
ядро
Online Access:http://dx.doi.org/10.1016/j.anucene.2017.11.045
Format: Electronic Book Chapter
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=657253

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