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

Detalles Bibliográficos
Parent link:Annals of Nuclear Energy
Vol. 113.— 2018.— [P. 286–293]
Autor Corporativo: Томский политехнический университет
Outros autores: 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
Idioma:inglés
Publicado: 2018
Subjects:
Acceso en liña:http://dx.doi.org/10.1016/j.anucene.2017.11.045
Formato: Electrónico Capítulo de libro
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=657253