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 [et al.]
Уровень набора: (RuTPU)RU\TPU\network\3526, Journal of Physics: Conference SeriesЯзык: английский.Страна: .Резюме или реферат: 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..Примечания о наличии в документе библиографии/указателя: [References: 17 tit.].Тематика: электронный ресурс | труды учёных ТПУ | реакторные установки | нейтронно-физические расчеты | топливо Ресурсы он-лайн:Щелкните здесь для доступа в онлайнНет реальных экземпляров для этой записи
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[References: 17 tit.]
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.
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