Waste form dissolution in bedded salt

descriptionPublicationkeyboard_double_arrow_right Report , Other literature type 16 Sep 1980 United States Publisher:Office of Scientific and Technical Information (OSTI)

Authors: Kaufman, A. M.;

doi: 10.2172/5114025

Waste form dissolution in bedded salt

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Abstract

A model was devised for waste dissolution in bedded salt, a hydrologically tight medium. For a typical Spent UnReprocessed Fuel (SURF) emplacement, the dissolution rate wll be diffusion limited and will rise to a steady state value after t/sub eq/ approx. = 250 (1+(1-epsilon/sub 0/) K/sub D//epsilon/sub 0/) (years) epsilon/sub 0/ is the overpack porosity and K/sub d/ is the overpack sorption coefficient. The steady state dissolution rate itself is dominated by the solubility of UO/sub 2/. Steady state rates between 5 x 10/sup -5/ and .5 (g/year) are achievable by SURF emplacements in bedded salt without overpack, and rates between 5 x 10/sup -7/ and 5 x 10/sup -3/ (g/year) with an overpack having porosity of 10/sup -2/.

Country

United States

Related Organizations

University of North Texas System
United States

Keywords

Steady-State Conditions, Radioactive Waste Storage, Storage, Geologic Deposits, & Storage, Waste Management, Water 052002* -- Nuclear Fuels-- Waste Disposal & Storage, Ground Water, Salt Deposits, 12 Management Of Radioactive And Non-Radioactive Wastes From Nuclear Facilities, Hydrogen Compounds, Spent Fuel Storage, Boreholes, Mathematical Models, Handling, Underground Storage, Waste Storage, Cavities, 11 Nuclear Fuel Cycle And Fuel Materials, Management, 050900 -- Nuclear Fuels-- Transport, Kinetics, Hydrology, Oxygen Compounds, Dissolution

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