Proceedings of the Sixth International Conference on Radioactive Waste Management and Environmental Remediation: ICEM '97 : Held in Singapore, October 12-16, 1997Rich Baker, Steven Slate, Gary Benda |
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Page 109
... surface contamination . Such criteria can be derived from the IAEA Transport Regulations ( 3 ) for the described types of mate- rials and packages . As liquid and gaseous wastes are excluded from final disposal in Germany in the ...
... surface contamination . Such criteria can be derived from the IAEA Transport Regulations ( 3 ) for the described types of mate- rials and packages . As liquid and gaseous wastes are excluded from final disposal in Germany in the ...
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 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 |
Development Work on the Current Options for the Management of Magnox Electric plc Radioactive Wastes | 89 |
Analysis of Natural Radionuclides in Lead and Environmental Management of Radioactive Lead | 103 |
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 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