Proceedings of the ... International Conference on Radioactive Waste Management and Environmental RemediationAmerican Society of Mechanical Engineers,., 1997 - Nuclear facilities |
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Page 285
... composition In this experiment , clay is used as sorption material , the result of clay measured shows the major composition is Illite . The particle size of clay used is 20-60 mesh , 60- 120 mesh , 120-160 mesh , 160-200 mesh in ...
... composition In this experiment , clay is used as sorption material , the result of clay measured shows the major composition is Illite . The particle size of clay used is 20-60 mesh , 60- 120 mesh , 120-160 mesh , 160-200 mesh in ...
Page 457
... composition by calcium oxide addition , shows that essentially all of the cerium and of the cobalt stayed in the glass as desired . Slag Quality Typical slag composition is shown in Fig . 4 . 70 Weight % 60 50 CO , were measured ...
... composition by calcium oxide addition , shows that essentially all of the cerium and of the cobalt stayed in the glass as desired . Slag Quality Typical slag composition is shown in Fig . 4 . 70 Weight % 60 50 CO , were measured ...
Page 472
... composition of the glasses . High Energy Radiations Absorbance In Fig . 1 the experimental appliance , used in order to evalu- ate the absorbance characteristics of the glasses , is shown . The high energy radiation source was a sample ...
... composition of the glasses . High Energy Radiations Absorbance In Fig . 1 the experimental appliance , used in order to evalu- ate the absorbance characteristics of the glasses , is shown . The high energy radiation source was a sample ...
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