THE HEAT CAPACITY OF BERYLLIUM CARBIDE POWDER IN STAINLESS STEEL CAPSULES AS A FUNCTION OF TEMPERATURE (400-1800 F)

The mean heat capacity of a sample of powdered beryllium carbide, a possible moderator material for a nuclear reactor, was determined as a function of temperature. A thin-walled stainless steel capsule containing the material was heated in an electric furnace and dropped into a water calorimeter. The following linear equation for mean heat capacity over the temperature range 50 f C-T f C as a function of temperature, T, was derived from the data by the method of least squares: C/sub p/ = 0.299 + 2.16 x 10/sup -4/ T f C el temperatures 0.005 cal gm/sup -1/( f C)/sup -1/. The numerical value of C/sub p/ expressed by this equation is also equal to the mean heat capacity in Btu lb/sup -1/( f F)/sup -1/. (auth

Twenty-five group reactor nuclear data tape neutron cross sections /

"United States Atomic Energy Commission contract no. AT(11-1)-171.""United States Air Force contract no. AF 33(600)-38062.""June 13, 1961.""UC-34 (16th ed.) TID 4500."General Electric Nuclear Materials and Propulsion Operation formerly known as Aircraft Nuclear Propulsion DepartmentMode of access: Internet