Modeling of 14C Diffusion from the Core of the Decommissioned ad Reactor; Atomic Energy; Vol. 118, iss. 5
| Parent link: | Atomic Energy Vol. 118, iss. 5.— 2015.— [P. 346-350] |
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| Autor Principal: | |
| Autor Corporativo: | |
| Outros autores: | , |
| 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 |
| Idioma: | inglés |
| Publicado: |
2015
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| Subjects: | |
| Acceso en liña: | http://dx.doi.org/10.1007/s10512-015-0005-7 |
| Formato: | Electrónico Capítulo de libro |
| KOHA link: | https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=646811 |
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| 200 | 1 | |a Modeling of 14C Diffusion from the Core of the Decommissioned ad Reactor |f M. V. Antonenko, D. O. Chubreev, G. V. Kuznetsov | |
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| 300 | |a Title screen | ||
| 320 | |a [References: p. 350 (8 tit.)] | ||
| 330 | |a 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. | ||
| 333 | |a Режим доступа: по договору с организацией-держателем ресурса | ||
| 461 | |t Atomic Energy | ||
| 463 | |t Vol. 118, iss. 5 |v [P. 346-350] |d 2015 | ||
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| 610 | 1 | |a электронный ресурс | |
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| 701 | 1 | |a Chubreev |b D. O. |g Dmitry Olegovich | |
| 701 | 1 | |a Kuznetsov |b G. V. |c Specialist in the field of heat power energy |c Professor of Tomsk Polytechnic University, Doctor of Physical and Mathematical Sciences |f 1949- |g Geny Vladimirovich |3 (RuTPU)RU\TPU\pers\31891 |9 15963 | |
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