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 439
... VOLUME REDUCTION BY COMPRESSING Yu Mingde , Liang Ying , Chang Jiang Northwest Institute of Nuclear Technology P. O. Box 69 , Xi'an 710024 , P. R. China ABSTRACT This paper describes an experiment of volume reduction by compressing fine ...
... VOLUME REDUCTION BY COMPRESSING Yu Mingde , Liang Ying , Chang Jiang Northwest Institute of Nuclear Technology P. O. Box 69 , Xi'an 710024 , P. R. China ABSTRACT This paper describes an experiment of volume reduction by compressing fine ...
Page 512
... volume to the volume of silt after vacuum filtration . TABLE III Results of Ground Treated with the Traditional Cementation Method Flowability * Ratio of final product volume to the volume of initial ground . TABLE IV Results of Silt ...
... volume to the volume of silt after vacuum filtration . TABLE III Results of Ground Treated with the Traditional Cementation Method Flowability * Ratio of final product volume to the volume of initial ground . TABLE IV Results of Silt ...
Page 513
... volume to the volume of final product ; ratio of initial ground volume to the volume of final product . TABLE V Comparison of Results of Treatment of Silts and Grounds by the Traditional Cementation Method with the Results of ...
... volume to the volume of final product ; ratio of initial ground volume to the volume of final product . TABLE V Comparison of Results of Treatment of Silts and Grounds by the Traditional Cementation Method with the Results of ...
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