The Thermal Conductivity of Uranium Monocarbide
Description:
Uranium carbide shows promise as a fuel material for reactors operating at relatively high temperatures based on its high melting point, high uranium density and high thermal conductivity. Before refined reactor designs can be made, however, good quantitative data on the thermal conductivity at temperatures in excess of 1000C is required. This technical report presents data gathered as part of a continuing study aimed at determining the thermal conductivity of refractory uranium fuels as a func…
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Date:
April 2, 1964
Creator:
Sobon, J. T.; Miller, A. D. & DeCrescente, M. A. (Michael A.)
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Report