Diffusion of Krypton Through Uranium Carbide - Final Report
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.
Date:
January 10, 1961
Creator:
Weinstock, J. J.; Pinkerton, A. P. & Ziegel, K. D.
Item Type:
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Report
Partner:
UNT Libraries Government Documents Department