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 230
... simulated HLW solution . Element TABLE I Compounds of Simulated HLW Na Fe AJ Ni Cr Cs K ᎡᏂ Sr Content g / 1 51.2 17.4 16.5 8.2 2.0 1.76 0.45 0.3 0.62 Times over Sr 82.6 28.1 26.6 13.2 3.2 2.83 0.73 0,5 1 Equilibrium Distribution of ...
... simulated HLW solution . Element TABLE I Compounds of Simulated HLW Na Fe AJ Ni Cr Cs K ᎡᏂ Sr Content g / 1 51.2 17.4 16.5 8.2 2.0 1.76 0.45 0.3 0.62 Times over Sr 82.6 28.1 26.6 13.2 3.2 2.83 0.73 0,5 1 Equilibrium Distribution of ...
Page 371
... simulated studies were carried out to understanding the stability of the former formula- tion of granite fissure water proposed by China Radiation Protect Institute ( CRPI ) using geochemical modeling code MINTEQA2 . The precipitation ...
... simulated studies were carried out to understanding the stability of the former formula- tion of granite fissure water proposed by China Radiation Protect Institute ( CRPI ) using geochemical modeling code MINTEQA2 . The precipitation ...
Page 647
... simulated heads all layers . 21 22 23 24 25 26 27 28 29 30. SIMULATED HEAD ( feet ) -10 -15 -20 25 -30 -35 XX -35 -30 -25 + + -15 -10 single constant - concentration CB source term and 12 site - specif- ic constant - concentration ...
... simulated heads all layers . 21 22 23 24 25 26 27 28 29 30. SIMULATED HEAD ( feet ) -10 -15 -20 25 -30 -35 XX -35 -30 -25 + + -15 -10 single constant - concentration CB source term and 12 site - specif- ic constant - concentration ...
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