Results from long-term dissolution tests using oxidized spent fuel

Results from long-term dissolution tests using oxidized spent fuel [electronic resource]

Two semi-static dissolution tests using oxidized PWR spent fuel specimens are being conducted under ambient hot cell conditions in Nevada Test Site J-13 well water and unsealed fused silica vessels. The test specimens were oxidized at 250°C in air to bulk oxygen-to-metal (O/M) values of 2.21 and 2.3...

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Bibliographic Details
Online Access: Online Access
Corporate Authors: Pacific Northwest Laboratory (Researcher), Pacific Northwest National Laboratory (U.S.) (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Las Vegas, Nev : Oak Ridge, Tenn. : United States. Dept. of Energy. Office of Civilian Radioactive Waste Management ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1990.
Subjects:
Storage.
Management.
Materials.
Actinides.
Water Moderated Reactors.
Reactor Materials.
Nuclear Fuels.
Water Cooled Reactors.
Metals.
Reactors.
Spent Fuels.
Radioactive Waste Storage.
Waste Storage.
Waste Management.
Dissolution.
Chemical Reactions.
Fuels.
Fission Product Release.
Quantity Ratio.
Pwr Type Reactors.
Elements.
Oxidation.
Energy Sources.
Management Of Radioactive And Non-radioactive Wastes From Nuclear Facilities.

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Call Number: E 1.99: conf-9011116--5
E 1.99: conf-9011116--5 Available

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