Proceedings of the ... International Conference on Radioactive Waste Management and Environmental RemediationAmerican Society of Mechanical Engineers,., 1997 - Nuclear facilities |
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Page 193
... cells . In the old design , the fuel assemblies are stored in one cell over two in a checkerboard pattern . The major functional requirements are then assured as follows : neutron emission absorbing by large water gap between fuel ...
... cells . In the old design , the fuel assemblies are stored in one cell over two in a checkerboard pattern . The major functional requirements are then assured as follows : neutron emission absorbing by large water gap between fuel ...
Page 194
... cells without any influence on cell strength . These two solutions are described hereafter . Borated Stainless Steel Type 1 racks This type of rack is dedicated to the storage of fresh fuel assemblies . Each storage cell consists of a ...
... cells without any influence on cell strength . These two solutions are described hereafter . Borated Stainless Steel Type 1 racks This type of rack is dedicated to the storage of fresh fuel assemblies . Each storage cell consists of a ...
Page 829
... Cell Cutting and Maintenance 4 7 Cell 07 ( dissolver ) 0.6 Cells 04 , 05 , 06 ( adjustment and centrifuge ) 1.5 Cell 08 ( 1st extraction cycle ) 2 1.8 Cell 011 ( 2nd extraction cycle ) ( 3 ) 1.6 1.6 0.9 1.5 30 42 Cell 010 ( solvent ...
... Cell Cutting and Maintenance 4 7 Cell 07 ( dissolver ) 0.6 Cells 04 , 05 , 06 ( adjustment and centrifuge ) 1.5 Cell 08 ( 1st extraction cycle ) 2 1.8 Cell 011 ( 2nd extraction cycle ) ( 3 ) 1.6 1.6 0.9 1.5 30 42 Cell 010 ( solvent ...
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