Ceramic Nuclear Fuels in the System ZrO2 - CaO - UO2

Ceramic Nuclear Fuels in the System ZrO2 - CaO - UO2

Author: J. H. Handwerk

Publisher:

Published: 1962

Total Pages: 34

ISBN-13:

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Potential nuclear fuels in the system ZrO2-CaO-UO2 were investigated. Cubic fluorite-type solid solutions, as indicated by x-ray diffraction patterns, were formed by sintering CaO-stabilized ZrO2 and U3O8 compacts in either air or H2. A continuous solid solution was found between urania and stabilized zirconia with H2 sintering at 1750 deg C. Air sintering produced a limited region of solid solution in the stabilized zirconia portion of the system at 1450 deg C. Results on phase identification, oxidation behavior, and water corrosion are presented.


The ZrO2 - CaO - UO2 Ceramic Fuel Fabrication for the EBWR Spiked Core Elements

The ZrO2 - CaO - UO2 Ceramic Fuel Fabrication for the EBWR Spiked Core Elements

Author: R. C. Lied

Publisher:

Published: 1961

Total Pages: 38

ISBN-13:

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A series of experiments was proposed in which the thermal output of the EBWR is increased to 100 Mw. The increase in thermal energy will be accomplished by inserting 32 spike elements in the initial fuel core. The fuel selected for the spike elements was a cubic solid solution in the system ZrO2- CaO-UO2.


CERAMIC NUCLEAR FUELS IN THE SYSTEM ZrO$sub 2$-CaO-UO$sub 2$. Final Report

CERAMIC NUCLEAR FUELS IN THE SYSTEM ZrO$sub 2$-CaO-UO$sub 2$. Final Report

Author:

Publisher:

Published: 1962

Total Pages:

ISBN-13:

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Potential nuclear fuels in the system ZrO/sub 2/-CaO-UO/sub 2/ were investigated. Cubic fluorite-type solid solutions, as indicated by x-ray diffraction patterns, were formed by sintering CaO-stabilized ZrO/sub 2/ and U/ sub 3/O/sub 8/ compacts in either air or H/sub 2/. A continuous solid solution was found between urania and stabilized zirconia with H/sub 2/ sintering at 1750 deg C. Air sintering produced a limited region of solid solution in the stabilized zirconia portion of the system at 1450 deg C. Results on phase identification, oxidation behavior, and water corrosion are presented. (auth).