MATEC Web Conf.
Volume 245, 2018International Scientific Conference on Energy, Environmental and Construction Engineering (EECE-2018)
|Number of page(s)||9|
|Section||Engineering Nets and Equipment|
|Published online||05 December 2018|
Investigation of the characteristics of the container for storage of radioactive waste of nuclear power plants with uranium-graphite reactors
Peter the Great St. Petersburg Polytechnic University, 29 Politekhnicheskaya street, 195251, Saint Petersburg, Russia
* Corresponding author: Kalyutik@yandex.ru
The article presents the results of the study of neutron-physical characteristics of the container for storage of radioactive waste of nuclear power plants with uranium-graphite reactors. The interaction of gamma quanta (in the energy range from 0.1 to 2 MeV) with the structural materials of the container is simulated. The numerical values of the parameters determining the radiation characteristic of the container with the estimation of the calculation error are obtained. The following main characteristics of the container are determined: the attenuation coefficient of the equivalent dose, the numerical factor of gamma radiation accumulation. These characteristics can be used to justify the radiation safety of the container, in particular when selecting protection materials, as well as when building additional heterogeneous protection barriers.
© The Authors, published by EDP Sciences, 2018
This is an open access article distributed under the terms of the Creative Commons Attribution License 4.0 (http://creativecommons.org/licenses/by/4.0), which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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