Proceedings of the ... International Conference on Radioactive Waste Management and Environmental RemediationAmerican Society of Mechanical Engineers,., 1997 - Nuclear facilities |
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Page 365
... brine saturated and pressurized or the repository may be connected by the borehole to an underlying pressurized brine reservoir ( Fig . 4 ) . In either case the flow of brine up the borehole has the potential of reaching the surface ...
... brine saturated and pressurized or the repository may be connected by the borehole to an underlying pressurized brine reservoir ( Fig . 4 ) . In either case the flow of brine up the borehole has the potential of reaching the surface ...
Page 425
... brine direct- ly below the repository . A correlation length of clustered brine encounters represents the average size of a brine reservoir in the Delaware Basin . Brine encounters are defined by reports of intersection of pressurized brine ...
... brine direct- ly below the repository . A correlation length of clustered brine encounters represents the average size of a brine reservoir in the Delaware Basin . Brine encounters are defined by reports of intersection of pressurized brine ...
Page 1012
... brine saturation is the most important sampled parameter affecting the amount of brine brought to the surface . The residual saturation effects direct brine release in two ways ; 1 ) The potential amount of brine that could reach the ...
... brine saturation is the most important sampled parameter affecting the amount of brine brought to the surface . The residual saturation effects direct brine release in two ways ; 1 ) The potential amount of brine that could reach the ...
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