This program was established to develop new information concerning the mechanism of diffusion of fission gases (krypton and xenon) through UO2 and UC. The work was to concentrated on measurements of diffusion rates in unirradiated materials in the temperature range of 1000°C to above 2000°C, these determinations being important to the projected use of refractory fuel materials in high-temperature, high-burnup reactors.
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Added Title:
Atomic Energy Commission Report NYO-9047
Description
This program was established to develop new information concerning the mechanism of diffusion of fission gases (krypton and xenon) through UO2 and UC. The work was to concentrated on measurements of diffusion rates in unirradiated materials in the temperature range of 1000°C to above 2000°C, these determinations being important to the projected use of refractory fuel materials in high-temperature, high-burnup reactors.
Physical Description
21 pages : illustrations, tables
Notes
Digitized from microopaque cards (1).
United States-Euraton Joint Research and Development Program
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Imaged from microcard, these technical reports describe research performed for U.S. government agencies from the 1930s to the 1960s. The reports were provided by the Technical Report Archive and Image Library (TRAIL).
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Weinstock, J. J.; Pinkerton, A. P. & Ziegel, K. D.Diffusion of Krypton Through Uranium Carbide - Final Report,
report,
January 10, 1961;
Washington D.C..
(https://digital.library.unt.edu/ark:/67531/metadc1463123/:
accessed February 13, 2025),
University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu;
crediting UNT Libraries Government Documents Department.