High-temperature oxidation of Zircaloy in hydrogen-steam mixtures. [PWR; BWR]

High-temperature oxidation of Zircaloy in hydrogen-steam mixtures. [PWR; BWR] [electronic resource]

Oxidation rates of Zircaloy-4 cladding tubes have been measured in hydrogen-steam mixtures at 1200 to 1700°C. For a given isothermal oxidation temperature, the oxide layer thicknesses have been measured as a function of time, steam supply rate, and hydrogen overpressure. The oxidation rates in the m...

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Online Access: Online Access
Corporate Authors: Argonne National Laboratory (Researcher), Electric Power Research Institute (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Argonne, Ill. : Oak Ridge, Tenn. : Argonne National Lab ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1982.
Subjects:
Safety.
Water Moderated Reactors.
Tin Alloys.
Uranium Compounds.
Reactor Safety.
Actinide Compounds.
Oxygen Compounds.
Reactor Cores.
Uranium Dioxide.
Elements.
Hydrogen.
Alloys.
Reactor Accidents.
Materials.
Nonmetals.
Reactor Materials.
Water Cooled Reactors.
Bwr Type Reactors.
Reactors.
Reactor Core Disruption.
Uranium Oxides.
Zircaloy 4.
Fuel Cans.
Chemical Reactions.
Pwr Type Reactors.
Oxides.
Reactor Components.
Zirconium Base Alloys.
Zirconium Alloys.
Accidents.
Steam.
Oxidation.
Zircaloy.
Chalcogenides.
General Studies Of Nuclear Reactors.

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Call Number: E 1.99:conf-820662-6
E 1.99:conf-820662-6 Available

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