Abstract. Measurements were made to determine the effect of thermal cycling on heat transfer from slug to jack using a slug with a sand blasted surface. The value of the transfer coefficient h decreased from initial values ranging from 10 to [formula], to values and [formula] after 1700 cycles, and to a range of 0.15 to 0.45 [formula] after 3200 cycles. Comparisons are made with the results found for slugs with different surfaces.

This memorandum, constitutes a report on the results of experiments conducted at the U. S. Waterways Experiment Station on a small scale model of that reach of the Mississippi River near and including Dogtooth Bend (Mile 32.7 above to Mile 4.0 below Cairo).

A report about elevated-temperature tensile properties of dilute uranium alloys. Alloys up to 2 a/o aluminum and 4 a/o zirconium have been fabricated to rod and are being tested at temperatures up to 500 C.

Report documenting the suitability of Virginia for plant locations to produce synthetic liquid fuels, based on raw materials, water sources, and local interest.

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.

The operating lives of Redox Process mechanical equipment are given. Tables are included which give the operating hours, reason for failure, position, and original date installed.

The purpose of this letter is to point out certain discrepancies between previous work on the decay of Rb82 (6.3 hour, B+, K-capture) and studies made recently at the University of California Radiation Laboratory.

A letdown valve design is described which reduces erosion of the sealing surfaces. It also provides for water flushing of the sealing surface before closing.

.Recalculations were made of HRT cell pressures in the event of a simultaneous rupture of the reactor core vessel and the fuel and blanket heat exchangers. These calculations will be applicable after the replacement fuel heat exchanger is installed. The pressure rise in the cell is plotted as a function of time. A maximum cell pressure of 34 psig is achieved ~7 sec after rupture.