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 482
... Carbon content ( wt % ) 90- 80- WA SA 70- SC Termination of smoking 60- 50- 40- 20- 10 0 0.5 1 Fig . 2. Experimental configuration for spent resins pyrolysis . Measurement of Carbon Content The carbon contents of the bland new resins ...
... Carbon content ( wt % ) 90- 80- WA SA 70- SC Termination of smoking 60- 50- 40- 20- 10 0 0.5 1 Fig . 2. Experimental configuration for spent resins pyrolysis . Measurement of Carbon Content The carbon contents of the bland new resins ...
Page 552
... carbon aerogels to quanti- fy the system efficiency and effectiveness . In the case study with the aged contaminated water ( stored at ambient conditions for 6 months ) , it is believed that bio - fouling and / or contaminants by ...
... carbon aerogels to quanti- fy the system efficiency and effectiveness . In the case study with the aged contaminated water ( stored at ambient conditions for 6 months ) , it is believed that bio - fouling and / or contaminants by ...
Page 558
... Carbon , ppm - wt medium , g added , Equiv . as C Carbon unoxidized , g C Extent of destruction 3.5 0 70 54 564 0 59060 3.17 0.0 3 1.4 140 1073 2.8 1.30 0.27 0.00073 0.99977 PFR - EO 3 ( continuous flow ) 0.00029 0.99991 2.5 TABLE IV ...
... Carbon , ppm - wt medium , g added , Equiv . as C Carbon unoxidized , g C Extent of destruction 3.5 0 70 54 564 0 59060 3.17 0.0 3 1.4 140 1073 2.8 1.30 0.27 0.00073 0.99977 PFR - EO 3 ( continuous flow ) 0.00029 0.99991 2.5 TABLE IV ...
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