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

I. V. Shamanin, V. V. Knyshev, A. I. Zorkin, M. E. Kuznetsova, I. V. Lutsik

Результат исследований: Материалы для журнала

Аннотация

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)O 2 , (Th,Pu)N, (Th,Pu)C), which can be included (dispersed) into the matrix of the fuel compact of the reactor under investigation. It has been established that the use of (Th, Pu) C-fuel will increase the burn-up of heavy metal by 5%, reduce the accumulation of fission products and CO, increase the service life of fuel.

Язык оригиналаАнглийский
Номер статьи012005
ЖурналJournal of Physics: Conference Series
Том1189
Номер выпуска1
DOI
СостояниеОпубликовано - 16 апр 2019
Событие7th International Scientific School-Conference of Young Scientists on Modern Problems of Physics and Technologies, MPPT 2018 - Moscow, Российская Федерация
Продолжительность: 16 апр 201821 апр 2018

ASJC Scopus subject areas

  • Physics and Astronomy(all)

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