Modeling of 14C Diffusion from the Core of the Decommissioned ad Reactor

Bibliographic Details
Parent link:Atomic Energy
Vol. 118, iss. 5.— 2015.— [P. 346-350]
Main Author: Antonenko M. V. Mikhail Viktorovich
Corporate Author: Национальный исследовательский Томский политехнический университет Энергетический институт Кафедра теоретической и промышленной теплотехники
Other Authors: Chubreev D. O. Dmitry Olegovich, Kuznetsov G. V. Geny Vladimirovich
Summary: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
Language:English
Published: 2015
Subjects:
Online Access:http://dx.doi.org/10.1007/s10512-015-0005-7
Format: Electronic Book Chapter
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=646811
Description
Summary: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
DOI:10.1007/s10512-015-0005-7