Determination of Diffusion Cooling in Graphite by Measurement of the Average Neutron Velocity (open access)

Determination of Diffusion Cooling in Graphite by Measurement of the Average Neutron Velocity

From Abstract: "The diffusion cooling coefficient in graphite has been determined by measuring the change in the asymptotic average velocity with buckling, by pulsed neutron methods. The times necessary to establish equilibrium spectra in graphite and heavy water have been measured and are reported."
Date: January 2, 1962
Creator: Starr, E. & De Villiers, J. W. L. (Jacobus Wynand Louw)
System: The UNT Digital Library
High Performance UO2 Program Third Quarterly Progress Report: October-December 1961 (open access)

High Performance UO2 Program Third Quarterly Progress Report: October-December 1961

The primary purpose of this joint USAEC-Euratom program is to obtain a better understanding of the maximum achievable operating characteristics of UO2 as a reactor fuel. During the program work will be performed in two areas that have been of concern to reactor core designers for a long time, namely, fission gas release and central melting in fuel rods.
Date: January 2, 1962
Creator: Weidenbaum, B.
System: The UNT Digital Library