Neutron-physical studies of ceramic fuel of a hightemperature reactor in the regime of long-term operation; Journal of Physics: Conference Series; Vol. 1189 : Modern problems of physics and technologies

Neutron-physical studies of ceramic fuel of a hightemperature reactor in the regime of long-term operation; Journal of Physics: Conference Series; Vol. 1189 : Modern problems of physics and technologies

Detalhes bibliográficos
Parent link:Journal of Physics: Conference Series
Vol. 1189 : Modern problems of physics and technologies.— 2019.— [012005, 4 p.]
Autor Corporativo: Национальный исследовательский Томский политехнический университет Школа базовой инженерной подготовки Отделение естественных наук
Outros Autores: Shamanin I. V. Igor Vladimirovich, Knyshev V. V. Vladimir Vladimirovich, Zorkin A. I. Andrey Igorevich, Kuznetsova M. E. Mariya Evgenjevna, Lutsik I. O. Igor Olegovich
Resumo:Title screen
In this paper, we present the results of studies of the physics of a high-temperature gas-cooled thorium reactor facility of low power operating in the long-term operation mode. Carried out a comparative neutron-physical calculation of promising fuel compounds ((Th,Pu)O2, (Th,Pu)N, (Th,Pu), which can be included (dispersed) into the matrix of the fuelcompact of the reactor under investigation. It has been established that the use of (Th, Pu) Cfuel will increase the burn-up of heavy metal by 5%, reduce the accumulation of fission products and CO, increase the service life of fuel.
Idioma:inglês
Publicado em: 2019
Assuntos:
электронный ресурс
труды учёных ТПУ
реакторные установки
нейтронно-физические расчеты
топливо
Acesso em linha:https://doi.org/10.1088/1742-6596/1189/1/012005
Formato: Recurso Eletrônico Capítulo de Livro
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=664448

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