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 452
... temperature and high - pressure working conditions and by possible reactor corrosion . The presence of chlorides in the waste feed stream may rapidly result in uncontrollable stress cor- rosion of the process reactor ( 7 ) . Moreover ...
... temperature and high - pressure working conditions and by possible reactor corrosion . The presence of chlorides in the waste feed stream may rapidly result in uncontrollable stress cor- rosion of the process reactor ( 7 ) . Moreover ...
Page 453
... Temperature ( ° C ) ( mg.11 ) 400 2100 420 1080 460 280 480 70 500 9 COD reduction ( molar % ) ( % ) 1.2 96.5 0.8 97.8 0.4 99.1 0.05 99.5 < 0.02 99.98 Temperature ( ° C ) CO concentration in 460 gaseous phase ( % ) 0.2 500 < 0.02 COD in ...
... Temperature ( ° C ) ( mg.11 ) 400 2100 420 1080 460 280 480 70 500 9 COD reduction ( molar % ) ( % ) 1.2 96.5 0.8 97.8 0.4 99.1 0.05 99.5 < 0.02 99.98 Temperature ( ° C ) CO concentration in 460 gaseous phase ( % ) 0.2 500 < 0.02 COD in ...
Page 482
... Temperature RESULTS Weight changes after 2 hours pyrolysis of the bland new resins in various temperatures are illustrated in Fig . 3. At 500 ° C , SA melted and adhered into the quartz tube wall , WA swelled up , while SC reduced its ...
... Temperature RESULTS Weight changes after 2 hours pyrolysis of the bland new resins in various temperatures are illustrated in Fig . 3. At 500 ° C , SA melted and adhered into the quartz tube wall , WA swelled up , while SC reduced its ...
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