Scientific Basis for Nuclear Waste Management VII: Symposium Held November 1983 in Boston, Massachusetts, U.S.A.G. L. McVay |
Contents
NUMERICAL AND EXPERIMENTAL INVESTIGATIONS ON THE TIME DEPENDENT | 1 |
CHEMICAL DURABILITY OF A MULTICOMPONENT GLASS IN A SIMULATED | 9 |
LABORATORY INVESTIGATIONS ON RADIOLYSIS EFFECTS ON ROCK SALT | 17 |
Copyright | |
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Common terms and phrases
actinides americium analysis aqueous aquifer backfill basalt Basis for Nuclear bentonite borehole borosilicate glass brine calculated canister carbonate ceramic chemical CHLW clay colloids composition concentration container corrosion decrease deionized water depth diffusion dissolution dose effects elements Elsevier Science Publishing emplacement environment estimates experimental experiments Figure flow rate fluid formation fracture geologic granite groundwater hydration hydraulic conductivity iron irradiation layer leach rate leachate material matrix measured mg/L migration minerals neptunium Nuclear Waste Nuclear Waste Management nuclides overpack oxidation Palo Duro Basin parameters particles performance phase potential predicted Proc radiation radioactive waste radionuclides ratio reaction redox rock salt samples saturation silica simulated solid solubility solution sorption species specimens spent fuel surface Symp SYNROC Table technetium temperature thermal tion Topopah Spring tuff uranium values waste form waste glass Waste Isolation waste package waste repository Yucca Mountain zeolites zone