Thermoelastic stresses in U-Pu-Zr ternary alloy fuels. An analytical interpretation of results in the IFR lead irradiation experiments

Thermoelastic stresses in U-Pu-Zr ternary alloy fuels. An analytical interpretation of results in the IFR lead irradiation experiments [electronic resource]

Thermoelastic stresses in U-Pu-Zr ternary alloy fuels with and without alloy redistribution and porosity formation have been calculated via a specially written computer program (IFR3R) developed for a composite cylinder analysis. The calculated thermoelastic stresses in a restructured three-zone U-P...

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Bibliographic Details
Online Access: Online Access (via OSTI)
Corporate Author: Argonne National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Washington, D.C. : Oak Ridge, Tenn. : United States. Department of Energy. ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 1986.
Subjects:
Ifr Reactor.
Nuclear Fuels.
Reactor Materials.
Ternary Alloy Systems.
Uranium Alloys.
Plutonium Alloys.
Zirconium Alloys.
Materials Testing.
Thermoelasticity.
Thermal Stresses.
Mathematical Models.
Burnup.
General Studies Of Nuclear Reactors.
Specific Nuclear Reactors And Associated Plants.
Materials Science.

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Call Number: E 1.99:anl-ifr--49
E 1.99:anl-ifr--49 Available

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