Immobilization of Cs-137 and Co-60 in concrete matrix. Part 2: Mathematical modeling of transport phenomena
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There are two fundamental issues that must be addressed in an attempt to isolate low-level waste in a disposal facility on land. The first is the isolation of waste from water, or hydrologic isolation. The second is prevention of radionuclide leakage from the disposal facility, or radionuclide migration. We have investigated here the latter modified scenario. Transport phenomena involved in the leaching of a radioactive material from a cement composite matrix have been investigated using an empirical method employing a polynomial equation. The results presented in this paper are examples of the results obtained from a 25-year mortar and concrete testing project, which will influence the design of the engineered trench system for a future central Serbian radioactive waste storage center. (c) 2005 Elsevier Ltd. All rights reserved.
Извор:Annals of Nuclear Energy, 2005, 32, 13, 1509-1515
ISSN: 0306-4549 (print)