This partially annotated bibliography contains references on advanced space propulsion units. References are also included on auxiliary power units, energy requirements, and mission requirements. The references are arranged alphabetically by title, with corporate author and subject indexes provided. This bibliography is issued in two parts: CNLM-2370-3, Part I, contains unclassified references; CNLM2370-3, Part II, contains classified material. Sources used in compiling this bibliography are: Abstracts of Classified Reports 1957-June 1960, Applied Science and Technology Index 1958-June 1960, ASTIA 1958-June 1960, Engineering Index 1957-1959, Industrial Arts Index 1957, Nuclear Science Abstracts 1957-June 1960, U.S. Government Publications Monthly Catalog 1958-June 1960.

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 function of temperature, density and composition over the temperature range 1000-2200C. At the inception of this program it was felt that an absolute method capable of achieving high temperatures was necessary and that the difficulties encountered in fabricating the large complex specimens needed were justified. The steady state radial heat flow method and apparatus of Rasor and McClelland were therefore chosen. The technical report discusses the experimental equipment and presents results of measurements on three specimens of UC over a temperature range 900 to 1600C. An analysis of the data is made with respect to other physical properties of the material and the measured conductivities are compared with the work of other investigators.