This is the second of two reports describing the phases of a study of the wear and galling of autoclaved Zircaloy-2 by various fuel element support materials. The first report (1) showed that increasing contact area between the autoclaved Zircaloy-2 support and the autoclaved Zircaloy-2 process tube will not significantly improve the fuel support performance, and that a large flat contact area between the fuel supports and the process tube would be impractical to endeavor to achieve and maintain. It also showed that metals softer than Zircaloy-2 do not scratch the process tube but that loss of these metals by …
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This is the second of two reports describing the phases of a study of the wear and galling of autoclaved Zircaloy-2 by various fuel element support materials. The first report (1) showed that increasing contact area between the autoclaved Zircaloy-2 support and the autoclaved Zircaloy-2 process tube will not significantly improve the fuel support performance, and that a large flat contact area between the fuel supports and the process tube would be impractical to endeavor to achieve and maintain. It also showed that metals softer than Zircaloy-2 do not scratch the process tube but that loss of these metals by abrasion into the reactor coolant might be a problem.
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Weber, J. W.A Study of the Wear and Galling of Various Fuel Element Support Materials on Autoclaved Zircaloy-2 Interim Report No. 2,
report,
March 1, 1960;
Washington D.C..
(https://digital.library.unt.edu/ark:/67531/metadc1255615/:
accessed October 9, 2024),
University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu;
crediting UNT Libraries Government Documents Department.