Proceedings of the ... International Conference on Radioactive Waste Management and Environmental RemediationAmerican Society of Mechanical Engineers,., 1997 - Nuclear facilities |
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Page 231
... Extraction of Pu ( IV ) The distribution coefficients ( D ) of Pu ( IV ) extracted by 0.2 mol / l PAIV were listed in Table X. The results obtained show that the PAIV possesses strong extraction ability for Pu ( IV ) . The D. decreases ...
... Extraction of Pu ( IV ) The distribution coefficients ( D ) of Pu ( IV ) extracted by 0.2 mol / l PAIV were listed in Table X. The results obtained show that the PAIV possesses strong extraction ability for Pu ( IV ) . The D. decreases ...
Page 233
... extraction for Am , Eu and Nd remains unchanged . Eu is most easily extracted and Am and Nd have about the same extractability . With this kind of extractant , Am can be separated from fission product lanthanides ( FPLns ) in a three ...
... extraction for Am , Eu and Nd remains unchanged . Eu is most easily extracted and Am and Nd have about the same extractability . With this kind of extractant , Am can be separated from fission product lanthanides ( FPLns ) in a three ...
Page 234
... Extraction of tracer amount of Am , Eu and Nd with dialkylphosphoric , phosphonic and phosphinic acids . EXTRACTION WITH MONO- AND DI - THIS SUBSTITUTED DIALKYLPHOPSHINIC ACIDS Cyanex 301 and Cyanex 302 produced by Cytec Inc. , Canada ...
... Extraction of tracer amount of Am , Eu and Nd with dialkylphosphoric , phosphonic and phosphinic acids . EXTRACTION WITH MONO- AND DI - THIS SUBSTITUTED DIALKYLPHOPSHINIC ACIDS Cyanex 301 and Cyanex 302 produced by Cytec Inc. , Canada ...
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