Modeling of 14C Diffusion from the Core of the Decommissioned ad Reactor; Atomic Energy; Vol. 118, iss. 5

Modeling of 14C Diffusion from the Core of the Decommissioned ad Reactor; Atomic Energy; Vol. 118, iss. 5

Podrobná bibliografie
Parent link:Atomic Energy
Vol. 118, iss. 5.— 2015.— [P. 346-350]
Hlavní autor: Antonenko M. V. Mikhail Viktorovich
Korporativní autor: Национальный исследовательский Томский политехнический университет Энергетический институт Кафедра теоретической и промышленной теплотехники
Další autoři: Chubreev D. O. Dmitry Olegovich, Kuznetsov G. V. Geny Vladimirovich
Shrnutí:Title screen
A mathematical model of the diffusion of radionuclides through engineered safety barriers is developed for 14C in order to determine the long-term safety conditions and characteristics of a decommissioned commercial uranium-graphite reactor. Dry and wet mixtures and concrete are used as the barrier materials. Diffusion is studied as the dominant mechanism for the transport of the radionuclides. The 14C concentration at the boundary between the radwaste storage site and the environment is determined computationally and the effect of the modeling conditions on the specific activity of the radionuclide is analyzed. The decomposition sequence of the safety barriers for which the 14C concentration is much lower than the admissible value is determined.
Режим доступа: по договору с организацией-держателем ресурса
Jazyk:angličtina
Vydáno: 2015
Témata:
труды учёных ТПУ
электронный ресурс
радионуклиды
безопасность
барьерные материалы
диффузия
реакторы
On-line přístup:http://dx.doi.org/10.1007/s10512-015-0005-7
Médium: Elektronický zdroj Kapitola
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=646811

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