Proceedings of the ... International Conference on Radioactive Waste Management and Environmental RemediationAmerican Society of Mechanical Engineers,., 1997 - Nuclear facilities |
From inside the book
Results 1-3 of 72
Page 459
... treatment facilities . The liquid and solid waste were collected in storage tanks and shelters . After many years of operation , the storage capabilities are exhausted . The treatment of the stored and still generat- ed waste represents ...
... treatment facilities . The liquid and solid waste were collected in storage tanks and shelters . After many years of operation , the storage capabilities are exhausted . The treatment of the stored and still generat- ed waste represents ...
Page 1023
... treatment . Since remaining ratio ( volatility ) during melting varies depending on the type of radionuclide , the scaling factor fluctuates before and after the melting treatment . Therefore , volatilation of each radionuclide is ...
... treatment . Since remaining ratio ( volatility ) during melting varies depending on the type of radionuclide , the scaling factor fluctuates before and after the melting treatment . Therefore , volatilation of each radionuclide is ...
Page 1024
... TREATMENT FACILITY In the Mihama plant , low level radioactive waste generated from the plant , concentrated liquid waste packed in metal drums TABLE III The Decomtamination Factor of the Ceramic Filter for the Off - gas from the ...
... TREATMENT FACILITY In the Mihama plant , low level radioactive waste generated from the plant , concentrated liquid waste packed in metal drums TABLE III The Decomtamination Factor of the Ceramic Filter for the Off - gas from the ...
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 | |
78 other sections not shown
Other editions - View all
Common terms and phrases
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