Neutron-physical studies of ceramic fuel of a hightemperature reactor in the regime of long-term operation
| Parent link: | Journal of Physics: Conference Series Vol. 1189 : Modern problems of physics and technologies.— 2019.— [012005, 4 p.] |
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| Співавтор: | |
| Інші автори: | , , , , |
| Резюме: | 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. |
| Мова: | Англійська |
| Опубліковано: |
2019
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| Предмети: | |
| Онлайн доступ: | https://doi.org/10.1088/1742-6596/1189/1/012005 |
| Формат: | Електронний ресурс Частина з книги |
| KOHA link: | https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=664448 |