Proceedings of the ... International Conference on Radioactive Waste Management and Environmental RemediationAmerican Society of Mechanical Engineers,., 1997 - Nuclear facilities |
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Page 478
... surface did not occur in the pH range from 3 to 11 ( 6 ) . However , the amount of Ce3 ion adsorbed on the sand surface increased as the increase of solution pH . The result from an aqueous solution is just opposite to that from the ...
... surface did not occur in the pH range from 3 to 11 ( 6 ) . However , the amount of Ce3 ion adsorbed on the sand surface increased as the increase of solution pH . The result from an aqueous solution is just opposite to that from the ...
Page 478
... surface in a given number of active sites . 2 0 2 10 12 14 PH -80 Fig . 7. Transfer coefficient and zeta potential against pH . In an aqueous solution , sorption of Cs + ion to the sand surface . did not occur in the pH range from 3 to ...
... surface in a given number of active sites . 2 0 2 10 12 14 PH -80 Fig . 7. Transfer coefficient and zeta potential against pH . In an aqueous solution , sorption of Cs + ion to the sand surface . did not occur in the pH range from 3 to ...
Page 567
... surface repository for the disposal of solid low - level and short - lived intermediate - level radioactive wastes at a remote and arid location . Site selection is in progress . Initially a GIS methodology was developed to assess data ...
... surface repository for the disposal of solid low - level and short - lived intermediate - level radioactive wastes at a remote and arid location . Site selection is in progress . Initially a GIS methodology was developed to assess data ...
Contents
DESCRIPTIONS OF NATIONAL ENVIRONMENTAL MANAGEMENT PROGRAMS | 1 |
A Service to National Community in Chile | 11 |
Cora Project The Italian Way for Conditioning High and Low Level Liquid Radioactive Wastes | 23 |
Copyright | |
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acid actinides activity analysis assessment backfill bentonite borehole brine burnup calculated canister carbon CCDF cell cement cesium chemical coefficient compaction composition concentration containing criteria decommissioning decontamination disposal facility dose drums effect Energy environment environmental evaluation extraction flow geological glass groundwater hydraulic IAEA incineration ion exchange ion exchange resins level waste material measured ment neptunium Nirex nitric acid nuclear fuel nuclear power nuclides operation organic oxidation parameters performance permeability phase plant plutonium polonium potential production radiation radioactive contamination Radioactive Waste Management radionuclides radwaste reactor reduce release repository reprocessing resins risk rock safety salt samples scenarios Sellafield simulated solid solution sorbent sorption specific spent fuel storage surface Table tank technetium temperature tests tion transport treatment uranium vitrification volume waste disposal waste form waste management waste packages WIPP zirconolite zone