Proceedings of the ... International Conference on Radioactive Waste Management and Environmental RemediationAmerican Society of Mechanical Engineers,., 1997 - Nuclear facilities |
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Page 272
... leaching rate . Leaching tests were conducted under stationary conditions in nitric acid concentrations of 104 mole / l at 25 ° C . The leaching data is pre- sent in Table III . With increase in the calcination temperatures of the ...
... leaching rate . Leaching tests were conducted under stationary conditions in nitric acid concentrations of 104 mole / l at 25 ° C . The leaching data is pre- sent in Table III . With increase in the calcination temperatures of the ...
Page 421
... leaching of the grout , and reconfiguration of the fissile material in to a more reactive geometry , within the boundaries of the original package . The development of the long term package dependent case is initiated by a Hazard and ...
... leaching of the grout , and reconfiguration of the fissile material in to a more reactive geometry , within the boundaries of the original package . The development of the long term package dependent case is initiated by a Hazard and ...
Page 591
... Leaching Scenario Intrusion Scenario SOAK WATERM DRILL NESOR AIRNT Drinking Vertical coordinate , cm Water -102 ... leaching fraction from waste form in leaching models . Usually , the diffusion coefficient used for the model is ...
... Leaching Scenario Intrusion Scenario SOAK WATERM DRILL NESOR AIRNT Drinking Vertical coordinate , cm Water -102 ... leaching fraction from waste form in leaching models . Usually , the diffusion coefficient used for the model is ...
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