Proceedings of the ... International Conference on Radioactive Waste Management and Environmental RemediationAmerican Society of Mechanical Engineers,., 1997 - Nuclear facilities |
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Page 293
... PERMEABILITY TESTS To assess the permeability of backfill material during the various stages of compaction , the BGR carries out permeability tests in a combined compaction - permeability apparatus . A cross section of this apparatus is ...
... PERMEABILITY TESTS To assess the permeability of backfill material during the various stages of compaction , the BGR carries out permeability tests in a combined compaction - permeability apparatus . A cross section of this apparatus is ...
Page 299
... permeability reduction by several orders of magnitude . Furthermore the simula- tions show a non - linear behaviour of the porosity and permeability variations in a core sample . A RADIATION ANNEALING MODEL FOR MAINTENANCE OF ...
... permeability reduction by several orders of magnitude . Furthermore the simula- tions show a non - linear behaviour of the porosity and permeability variations in a core sample . A RADIATION ANNEALING MODEL FOR MAINTENANCE OF ...
Page 301
... permeability decreases exponen- tially with the porosity , the differences in permeability between the inflow and outflow side are much greater than the differ- ences in porosity . Due to the decrease of the permeability , the brine ...
... permeability decreases exponen- tially with the porosity , the differences in permeability between the inflow and outflow side are much greater than the differ- ences in porosity . Due to the decrease of the permeability , the brine ...
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