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 591
... Leaching Scenario Intrusion Scenario SOAK WATERM DRILL NESOR AIRNT Drinking BREAK EXCOV Water Inhalation FOODT ... 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 BREAK EXCOV Water Inhalation FOODT ... leaching fraction from waste form in leaching models . Usually , the diffusion coefficient used for the model is ...
Page 771
... leaching process , the specific activity of soil a can be approximated as a function of individual abundance x ... leaching ( chemical extraction ) processes , when the mass g of the soil is contacted with volume V of leaching ...
... leaching process , the specific activity of soil a can be approximated as a function of individual abundance x ... leaching ( chemical extraction ) processes , when the mass g of the soil is contacted with volume V of leaching ...
Page 772
... leaching step , e.g. , from the first and second leaching data there is aj - 92-92 1 + q2 - 291 2 ( 10 ) Only when q , q , is achieved ( i.e. , retaining activity remains nearly constant at two steps of leaching ) , a , = q , can a true ...
... leaching step , e.g. , from the first and second leaching data there is aj - 92-92 1 + q2 - 291 2 ( 10 ) Only when q , q , is achieved ( i.e. , retaining activity remains nearly constant at two steps of leaching ) , a , = q , can a true ...
Contents
DESCRIPTIONS OF NATIONAL ENVIRONMENTAL MANAGEMENT PROGRAMS | 1 |
A Service to National Community in Chile | 11 |
Cor a 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 BTEX 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 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