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Scientific Basis for Nuclear Waste Management XXIII：VOLUME608
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The 114 papers cover fuel cladding and spent nuclear fuel, container fabrication and corrosion, performance assessment, repository performance, radionuclide sorption and transport, cement-based material and waste containment, the corrosion of ceramic wasteforms, the structure and characterization of ceramics, radiation effects, natural analogues, characterizing and processing wasteforms, and the corrosion and characterization of glass wasteforms. Among the invited papers are discussions of the impacts of alpha-radiolysis in spent fuel dissolution, fabricating and testing copper canisters for the long-term isolation of spent nuclear fuel, and simulating radionuclide migration in groundwater away from an underground nuclear test. Annotation c. Book News, Inc., Portland, OR (booknews.com)
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