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AbstractAbstract
[en] The ID-based migration code MIVID-R was set up, making it possible to model radionuclide migration through a bentonite layer for variable forms of the boundary and starting conditions while taking into account gradual corrosion degradation of the spent fuel, and to set up balance of the nuclide in question in the container. The retardation of the dominant transport phenomenon, ie., diffusion, is regarded as dependent on the nonlinear shape of the sorption isotherm. With regard to the expected shape of the container and of the surrounding bentonite layer, the code is set up for the cylindrical configuration. The code solves the basic migration equation by the finite difference method and makes possible treatment of simultaneous migration of a set of nuclides which are interrelated by a genetic chain or which compete with each other in sorption
Original Title
Modelovani transportu kritickych radionuklidu v oblasti inzenyrskych barier trvaleho uloziste vyhoreleho jaderneho paliva
Primary Subject
Source
Faculty of Nuclear Science and Physical Engineering, Czech Technical University, Prague (Czech Republic); [104 p.]; Oct 1998; p. 82; Nukleonika '98; Prague (Czech Republic); 9-10 Sep 1998
Record Type
Miscellaneous
Literature Type
Conference
Report Number
Country of publication
CALCULATION METHODS, CHEMICAL REACTIONS, CLAYS, COMPUTER CODES, CONFIGURATION, ENERGY SOURCES, ENVIRONMENTAL TRANSPORT, FUELS, INORGANIC ION EXCHANGERS, ION EXCHANGE MATERIALS, ITERATIVE METHODS, MANAGEMENT, MASS TRANSFER, MATERIALS, MINERALS, NUCLEAR FUELS, NUMERICAL SOLUTION, REACTOR MATERIALS, SILICATE MINERALS, WASTE DISPOSAL, WASTE MANAGEMENT
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