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 292
... bentonite are being considered and tested as backfill material for the WIPP site , the planned permanent repository for radioactive waste in the USA ( 3 ) . An addition of 30 % bentonite is considered to be the optimum . The objective ...
... bentonite are being considered and tested as backfill material for the WIPP site , the planned permanent repository for radioactive waste in the USA ( 3 ) . An addition of 30 % bentonite is considered to be the optimum . The objective ...
Page 314
... Bentonite Pore Water Under the Reducing Condition A STUDY ON THE WATER TRANSPORT IN BACKFILL MATERIAL Jae. 9 . B ... bentonite pore water chemistry in Table AI was calcu- lated assuming the following reactions ( 8 ) : 1 ...
... Bentonite Pore Water Under the Reducing Condition A STUDY ON THE WATER TRANSPORT IN BACKFILL MATERIAL Jae. 9 . B ... bentonite pore water chemistry in Table AI was calcu- lated assuming the following reactions ( 8 ) : 1 ...
Page 315
... bentonite is determined as Backfill / Buffer material , the properties of bentonite saturation time and hydraulic conductivity were measured . INTRODUCTION The multibarrier concept of radioactive waste repository has been introduced for ...
... bentonite is determined as Backfill / Buffer material , the properties of bentonite saturation time and hydraulic conductivity were measured . INTRODUCTION The multibarrier concept of radioactive waste repository has been introduced for ...
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