Proceedings of the ... International Conference on Radioactive Waste Management and Environmental RemediationAmerican Society of Mechanical Engineers,., 1997 - Nuclear facilities |
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Page 107
... waste management activities . Therefore a waste package has to be characterized and designed from the beginning in such a way , that requirements on the waste itself and the packaging resulting from transport regulations are taken into ...
... waste management activities . Therefore a waste package has to be characterized and designed from the beginning in such a way , that requirements on the waste itself and the packaging resulting from transport regulations are taken into ...
Page 110
... packages . Package Designs for Fissile Material If the radioactive waste in a IP- , Type A- or Type B package contains fissile material in form and quantities not excepted from the requirements for packages containing fissile material ...
... packages . Package Designs for Fissile Material If the radioactive waste in a IP- , Type A- or Type B package contains fissile material in form and quantities not excepted from the requirements for packages containing fissile material ...
Page 420
... packages within it can impose more restrictive package fissile limits than the stor- environment . This is due to the need to consider factors such ... waste stack leading to corrosion of 420 Palmer CRITICALITY SAFETY OF WASTE PACKAGES.
... packages within it can impose more restrictive package fissile limits than the stor- environment . This is due to the need to consider factors such ... waste stack leading to corrosion of 420 Palmer CRITICALITY SAFETY OF WASTE PACKAGES.
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