Proceedings of the ... International Conference on Radioactive Waste Management and Environmental RemediationAmerican Society of Mechanical Engineers,., 1997 - Nuclear facilities |
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Page 243
... cesium from Fig . 4. Comparison of the breakthrough of " Sr through SrTreat - A HIGHLY EFFECTIVE ION EXCHANGER FOR THE REMOVAL. sorption isotherms because the practical sorption capacities were measured ( 8 ) for different cesium ...
... cesium from Fig . 4. Comparison of the breakthrough of " Sr through SrTreat - A HIGHLY EFFECTIVE ION EXCHANGER FOR THE REMOVAL. sorption isotherms because the practical sorption capacities were measured ( 8 ) for different cesium ...
Page 281
... cesium in the high level liquid radioactive waste ( HLLW ) separation process developed in the People's Republic of China . The solidification study in this paper indicates that a titanate ceramic waste form consisting hollandite ( BaAl ...
... cesium in the high level liquid radioactive waste ( HLLW ) separation process developed in the People's Republic of China . The solidification study in this paper indicates that a titanate ceramic waste form consisting hollandite ( BaAl ...
Page 282
... cesium ions can be well inhibited in a cage formed by the 8 surrounding oxygen atoms . So it exhibits good leach resistance and is a very good vehicle for the immobilization of cesium . According to this , eight samples are made under ...
... cesium ions can be well inhibited in a cage formed by the 8 surrounding oxygen atoms . So it exhibits good leach resistance and is a very good vehicle for the immobilization of cesium . According to this , eight samples are made under ...
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