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PROBLEMS OF RADIOACTIVE WASTE DISPOSAL
Название Migration model to estimate safety of ultimate underground disposal of high-level waste and spent fuel in hard rocks
DOI 10.17580/gzh.2015.10.09
Автор Melnikov N. N., Amosov P. V.
Информация об авторе

Author 1:
Name & Surname: Melnikov N. N.
Company: Mining Institute, Kola Science Center (Apatity, Russia)
Work Position: Research Manager of Institute
Scientific Degree: Academician of the Russian Academy of Sciences
Contacts: root@goi.kolasc.net.ru


Author 2:
Name & Surname: Amosov P. V.
Company: Mining Institute, Kola Science Center (Apatity, Russia)
Work Position: Senior Researcher, Assistant Professor
Scientific Degree: Candidate of Engineering Sciences

Реферат

In the framework of the integrated scientific–technical problem solution aimed at radioactive waste management safety for the population and eco-systems, the Mining Institute of the Kola Science Center, Russian Academy of Sciences, has developed and presents in this article the migration model for estimation of conditions and parameters of radionuclides migration to biosphere from Russia’s projected federal repositories for ultimate disposal and isolation of high-level waste (HLW) and radioactive waste (RAW) in hard rock masses. The model is a methodology (methodological sample) of the analysis and estimation of safe underground RAW disposal implemented in a program code developed based on mathematical models and physical concepts, enabling identification of the most important conditions and trajectories of migration of radionuclides; calculation of the equivalent radiation dosage rate dynamics and contribution of individual radionuclides to the overall exposure; and information support for the RAW disposal designers to choose a disposal area and optimize engineering solutions. The authors show the ways of improving the migration model by means of expanded description of leaching of radionuclides from RAW matrix and by considering influence exerted by physico-mechanical properties of fracture filler and the migrating radioactive isotopes (density, porosity, sorption properties). The authors highlight good conformity of calculated data on radiation released from hypothetical ultimate disposal of a single spent fuel cask using computer codes developed by EC-JRC (Holland) and the Mining Institute of the Kola Science Center.

Ключевые слова Ultimate RAW disposal, hard rock mass, fractures, migration of radionuclides, migration model, program code, filler, physicochemical properties, equivalent radiation dosage rate, safety of object
Библиографический список

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