Proceedings of the ... International Conference on Radioactive Waste Management and Environmental RemediationAmerican Society of Mechanical Engineers,., 1997 - Nuclear facilities |
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Page 461
... sorbent . As sorbent nickelferrocyanide using aluminum silicate as a carrier material has been tested ( NSHA - Sorbent ) . The hourly throughput is equal 2 to 3 volumes of the sorbent . The loading capacity of the sorbent is in the ...
... sorbent . As sorbent nickelferrocyanide using aluminum silicate as a carrier material has been tested ( NSHA - Sorbent ) . The hourly throughput is equal 2 to 3 volumes of the sorbent . The loading capacity of the sorbent is in the ...
Page 463
... sorbent is not blocked by the above mentioned ions . PROCESS PARAMETER The NGC - Sorbent was tested in a pilot plant at NPP Balakovo . A throughput of 50.000 of sorbents volumes was achieved and the Cs - activity of the waste water was ...
... sorbent is not blocked by the above mentioned ions . PROCESS PARAMETER The NGC - Sorbent was tested in a pilot plant at NPP Balakovo . A throughput of 50.000 of sorbents volumes was achieved and the Cs - activity of the waste water was ...
Page 519
... sorbent . The sorbent is nickelferrocyanide using aluminium silicate as a carrier material ( NSHA - sorbent ) . The throughput is equal 2 to 3 volumes of the sorbent per hour . The loading capacity of the sorbents is in the range of 200 ...
... sorbent . The sorbent is nickelferrocyanide using aluminium silicate as a carrier material ( NSHA - sorbent ) . The throughput is equal 2 to 3 volumes of the sorbent per hour . The loading capacity of the sorbents is in the range of 200 ...
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