Proceedings of the Sixth International Conference on Radioactive Waste Management and Environmental Remediation: ICEM '97 : Held in Singapore, October 12-16, 1997Rich Baker, Steven Slate, Gary Benda |
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Page 419
... 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 ( ILW and LLW ) arising in ...
... 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 ( ILW and LLW ) arising in ...
Page 420
... packages within it can impose more restrictive package fissile limits than the stor- age environment . This is due to the need to consider factors ... 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- age environment . This is due to the need to consider factors ... waste stack leading to corrosion of 420 Palmer CRITICALITY SAFETY OF WASTE PACKAGES.
Page 435
... WASTE PACKAGES Gu Binxi and Zhang Xiaoyu Beijing Institute of Nuclear Engineering Liu Youping and Song Yixin Beijing University of Chemical Technology ABSTRACT According to the medium inside and outside the waste packages as well as the ...
... WASTE PACKAGES Gu Binxi and Zhang Xiaoyu Beijing Institute of Nuclear Engineering Liu Youping and Song Yixin Beijing University of Chemical Technology ABSTRACT According to the medium inside and outside the waste packages as well as the ...
Contents
DESCRIPTIONS OF NATIONAL ENVIRONMENTAL MANAGEMENT PROGRAMS | 1 |
A Service to National Community in Chile | 11 |
Cor a 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 BTEX burnup calculated canister carbon CCDF cell cement cesium chemical coefficient compaction composition concentration containing criteria 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 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