Proceedings of the ... International Conference on Radioactive Waste Management and Environmental RemediationAmerican Society of Mechanical Engineers,., 1997 - Nuclear facilities |
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Page 419
CRITICALITY SAFETY OF WASTE PACKAGES CONTAINING FISSILE MATERIAL IN A DEEP WASTE REPOSITORY John Palmer , Simon Wisbey , Michelle Wise United Kingdom Nirex Ltd ABSTRACT Solid intermediate- and certain low - level radioactive wastes ...
CRITICALITY SAFETY OF WASTE PACKAGES CONTAINING FISSILE MATERIAL IN A DEEP WASTE REPOSITORY John Palmer , Simon Wisbey , Michelle Wise United Kingdom Nirex Ltd ABSTRACT Solid intermediate- and certain low - level radioactive wastes ...
Page 420
... safety case is that the K of 0.95 represents the maximum reactivity of the pack- ages within the system at any time in the repository , allowing for the effects of package degradation . eff Work has shown that , in order to maintain ...
... safety case is that the K of 0.95 represents the maximum reactivity of the pack- ages within the system at any time in the repository , allowing for the effects of package degradation . eff Work has shown that , in order to maintain ...
Page 641
... safety case for the facility and therefore on the requirements of the design ; this will be reflected in the provisions of the licence . Repository Design International guidance ( 3 ) states that the conceptual reposi- tory design ...
... safety case for the facility and therefore on the requirements of the design ; this will be reflected in the provisions of the licence . Repository Design International guidance ( 3 ) states that the conceptual reposi- tory design ...
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