Proceedings of the ... International Conference on Radioactive Waste Management and Environmental RemediationAmerican Society of Mechanical Engineers,., 1997 - Nuclear facilities |
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Page 255
... acid scrubbing of technetium was shown in a basic study and a chemical flowsheet study . Fig . 5. Destruction fruction of n - butyraldehyde as. INTRODUCTION Development of an advanced PUREX process has been con- ducted which can reduce ...
... acid scrubbing of technetium was shown in a basic study and a chemical flowsheet study . Fig . 5. Destruction fruction of n - butyraldehyde as. INTRODUCTION Development of an advanced PUREX process has been con- ducted which can reduce ...
Page 257
... Acid The reaction heat of n - butyraldehyde with nitric acid was measured by a differential thermogravimetry method ( DTA ) from a safety point of view in the process usage . The reaction is an exothermic reaction . Figure 6 shows ...
... Acid The reaction heat of n - butyraldehyde with nitric acid was measured by a differential thermogravimetry method ( DTA ) from a safety point of view in the process usage . The reaction is an exothermic reaction . Figure 6 shows ...
Page 544
... Acid Water Asid Recovery Concentrated Silver Chloride Acid Heater Dissolver Heat Exchanger To Water Treatment Heat Exchanger P.S.N Ac , Inera To Final Forme Pump Pump Demister Demister out out 02 To Process Oligas Heat Exchanger Heat ...
... Acid Water Asid Recovery Concentrated Silver Chloride Acid Heater Dissolver Heat Exchanger To Water Treatment Heat Exchanger P.S.N Ac , Inera To Final Forme Pump Pump Demister Demister out out 02 To Process Oligas Heat Exchanger Heat ...
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