From Forward: "Although the first paper in this volume describes the general aspects of the technical management of the program, it is important to emphasize that much of success and productivity of this program stemmed from the sympathetic understanding of its basic viewpoint by both the Department of Defense and the National Bureau of Standards."

From Present Programs: "There has been a gradual expansion of the Sr^90 food analysis program to include vegetable foods and finally entire diets. In some cases the analyses have also been extended to other nuclides but these data are so limited that they will not be emphasized in this report. It is expected that considerable data on Ra^226 and other naturally occurring radionuclides will be generated in coming year."

From Abstract: "These data are important for personnel protection on a national basis in the event of war and on a local basis in the event of certain types of nuclear accidents. This report discusses the need for such information and suggests methods for obtaining it."

Report describing the design of a Fast Fuel Test Reactor (FFTR), analyses of of the reactor's operations, related costs, and possible future projects.

From Introduction: "This report describes tests conducted on EBWR to evaluate the vapor recovery system."

From Introduction: "The study of the conversion of saline water by direct freezing using a secondary refrigerant has been sponsored by the the Office of Saline Water at Cornell University since the beginning of 1958. This report first considers the energy relationships which can be the basis for much controversy regarding the freezing process."

Report that summarizes the potential hazards of the Hanford Critical Mass Laboratory and presents operation procedures which will limit the probability of a nuclear accident. The report also outlines the planned experimental program, descriptions of the facility, and the administration of nuclear safety in the laboratory.

Report discussing the dissolution of simulated fuel cores. Equipment and procedures are discussed along with significant characteristics of the core materials.

Report discussing the "equilibrium uranium distribution between an aqueous nitric acid solution and a 30 per cent by volume solution of tributyl phosphate in a hydrocarbon diluent" (p. 2). This includes the necessary equations.

Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Homogeneous Reactor Program. It includes descriptions of progress and studies conducted during the report period, with tables, illustrations, and photographs.

Abstract: This report presents the vapor pressures versus temperature data graphically for the rare earth elements, yttrium and scandium.

Abstract: This report describes a 300,000-kwe, sodium-cooled, graphite-moderated nuclear power plant based on existing technical information.

Abstract: This report summarizes data developed at the Instrument and Controls Division, Oak Ridge National Laboratory on low noise amplifiers used with solid state detectors.

Quarterly report describing progress on a project to develop and evaluate high-temperature tungsten alloys. This report discusses experimentation with fabrication to improve thermal stability of tested combinations by further alloying.

Abstract: A definitive investigation of the boron-carbon equilibrium system is being made by X-ray diffraction, metallographic, and thermal analytical techniques. Alloys are being produced by sintering pressed powder aggregates with subsequent arc melting. Alloys have been made at two atomic percent intervals up to thirty atomic per cent carbon. In the future, higher carbon compositions are to be investigated. Techniques have been worked out for the metallographic preparation of the extremely hard and friable alloys.

The Irradiation Test Program for the Consolidated Edison Thorium Reactor was conducted to obtain confirmation of the stability and performance of the reference fuel element materials and of test assemblies under design operation conditions. The irradiated specimens were tested to determine mechanical properties and corrosion resistance to borated water.

The adequacy of the Consolidated Edison Thorium Reactor (CETR) control rod drive line operation was evaluated and proven by the development program described in this report. This program also included evaluation of materials and fabrication processes.

The Consolidated Edison Thorium Reactor Control System has been designed to provide the operators with a reliable, safe and accurate means of controlling the plant. Manual and automatic positioning of control rods can be accomplished. The automatic plant controller has been designed to meet the design criteria under the representative CETR demanded load changes. Adaptability has been built into the plant controller by providing variable controller adjustments for variations in reactor characteristics. Extensive analog studies have been made of the various plant parameters and their effect on control was carefully evaluated. These analog studies have shown that the control system will perform in a satisfactory manner under the most adverse plant conditions.

A study has been performed to determine the corrosion product and water impurity activities in the CETR Chemical Process System. A simplified mathematical model is used to represent the physical situation; however, the magnitude of the activities, taken at the end of the core life to represent the most conservative case, is considered sufficiently accurate for engineering calculations.

Prototype testing and thorough design analyses have proven the control components for the Consolidated Edison Thorium Reactor are adequate to withstand loads imposed during operation and handling. Assumptions made in the design analyses and cycles run during prototype testing subjected the components to more rigid conditions that are anticipated during actual operation. Results indicate the control components meet their design requirements.

Technical report. From Abstract: "A method was developed for fabricating tubular fuel elements of uranium dioxide by swage compaction of crushed, fused UO2. The elements were 5 to 10 feet long and were clad with stainless steel. UO2 densities up to 91% of theoretical were obtained in tubes about 2.1 inches in outside diameter and 0.3 inch in wall thickness."

Abstract: Development of welding processes for stainless steel fuel elements, previously initiated by Alco Products, was continued in Task 5. Three objectives were accomplished; (1) development of a suitable reference welding process, (2) evaluation by out-of-pile tests of the structural integrity of reference welded fuel elements, and (3) preparation of specifications and fabrication procedures for the reference welding process.

This report deals with the structural and lithologic features within and adjacent to the San Juan mineral belt and the relation of these features to the ore deposits.

Abstract. A method is described for measuring the molecular flow conductance of scale models of complete diffusion pump systems. Results are given in terms of Clausing's factor P, defined by P= F/F(0), where F is the net volume flow rate through a geometry and F(0) is the volume flow rate of gas striking the orifice of the geometry. Use of the factor P allows prediction of the conductance of the full-scale system represented by the model. Experimental and theoretical data are presented for straight cylinders, cylindrical elbows, and several geometries having no-line-of-sight through them. It is shown that for an optimized diffusion pump system, comprising baffle, trap and valve, 0.3 [less than] P [less than] 0.5 can be obtained.