Neutron-physical studies of ceramic fuel of a hightemperature reactor in the regime of long-term operation

Neutron-physical studies of ceramic fuel of a hightemperature reactor in the regime of long-term operation

Bibliographic Details
Parent link:Journal of Physics: Conference Series
Vol. 1189 : Modern problems of physics and technologies.— 2019.— [012005, 4 p.]
Corporate Author: Национальный исследовательский Томский политехнический университет Школа базовой инженерной подготовки Отделение естественных наук
Other Authors: 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
Summary: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.
Published: 2019
Subjects:
электронный ресурс
труды учёных ТПУ
реакторные установки
нейтронно-физические расчеты
топливо
Online Access:https://doi.org/10.1088/1742-6596/1189/1/012005
Format: Electronic Book Chapter
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=664448

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