Abstract: "Tungsten-rich alloys, developed for use at temperatures up to 2000F, exhibit ductility, fabricability and joinability not found in commercially-available materials. An envelope type of microstructure was produced in compositions containing at least 90 wt% tungsten by liquid-phase sintering of cold-pressed powders in hydrogen. At room temperature the alloys could be rolled extensively, and tensile elongations up to 25% were noted. Strength properties of a W-Ni-Fe base were improved by small quaternary additions. The ultimate tensile strength of a 90W-4.8Ni-3.2Fe-2Ru alloy was 46,700 psi at 2000F, compared to 30,000 - 35,000 psi for unalloyed tungsten or W-Ni-Fe; the 100-hour stress-rupture strength at 1600F was 15,000 psi. Excellent joints were produced by spot welding and localized induction heating. The oxidation resistance of unprotected 90 wt% tungsten compositions was not significantly affected by alloying."

The following document is a note describing the process of building a nuclear density gauge and its improved features in comparison to previously reported density gauges.

A report discussing "an explosive ferroelectric power supply and the experimental approach followed in determining its operating characteristics."

Abstract: An alluminum-clad low-enrichment, uranium-alloy fuel element of flat plate configuration has been proposed for the Organic Moderated Reactor (OMR).

Introduction: A low-capacity, low-decontamination plant can be built, as part of a power reactor complex, to avoid long distance transfer of fuel to a high-capacity aqueous processing plant. Activation of such a complex, with the processing plant adjacent to the reactor it serves, could decrease the cost of the integrated fuel cycle. The study of this concept is a major objective of the Processing Refabrication Experiment (PRE).

From abstract: "A relationship is derived that predicts the power radiated from the cathode to the anode of the plasma diode. The radiated power loss predicted by this relationship for a tungsten cathode and a nickel anode at widely different temperatures is found to be five times greater than the prediction of the conventional relationship which assumes gray-body conditions."

This report analyzes the High-Energy Electrostatic Plasma Gun, which is to be used for propulsion.

From introduction: The Commission's underlying objective of this program is to conduct sufficient engineering and development work to determine the most feasible and economical methods of producing nuclear super-heated steam from a boiling water reactor.

Abstract: During the course of power run 14 on the Sodium Reactor Experiment (SRE) at low power, the temperature difference among various fuel channels was found to be undesirably high. Normal operating practices did not succeed in reducing this temperature difference to acceptable values and on July 26, 1959, the run was terminated.

The diffusion coefficient was calculated for the diffusion of Xe through Nb and found to be 0.064 exp (-18,600/RT).

From introduction: The objective of this program is the development of a nuclear physical model and its calculation code for pressurized-water cooled and moderated reactors to predict accurately reactivity, rod positions and power distributions at operating temperatures, and reactor life from a nuclear standpoint.

From introduction: This report is a summary of geologic information obtained by the USGS at Dolomite Hill, Nevada.

The basic scheme for processing power reactor fuels at Hanford includes the removal of inert endfittings ("hardware") from the active sections of the fuels. Within Hanford Laboratories, research and development studies have been in progress on various types of saws which might be used for hardware cutoff. In the initial phase of the program, high-speed saws were investigated; more recently, studies on low speed saws have been conducted. This report summarizes the high speed saw studies and includes information on abrasive wheels, diamond wheels and metal "friction" blades which cut by actually melting metal ahead of the saw blade. At the completion of the low speed saw testing program currently in progress, basic saw types will be compared and the saw type to be included in the reprocessing complex will be selected.

The first series tests in the KER-REP-1 loop proved that a fisssion product contaminated loop could be decontaminated to a safe level for contact maintenance. The second series of tests ere scheduled for a more thorough evaluation of these processes includes specific decontamination factors, process corrosion rates, loop activity reduction factors (loop decontamination factors), and any preferential decontamination which may be present.

Considerable interest has developed in the use of ion-exchange in the nuclear energy field in the last decade. Aside from the obvious use of providing demineralized coolant water for reactors, the projected uses of ion-exchange include the recovery of fission products from aquaeous waste streams and the separation and purification of fissionable materials from spent reactor fuels. The latter process may be incidental to the over-all operation, as is the case with the Purex anion exchange facility, or it may be the prime separation process, as may be the case in the recovery of Pu or U from spent power reactor (PRTR) fuel elements.

Report documenting the investigation of cosmic and terrestrial background radiation. "Remeasurements in many locations furnished estimates of dosimetric increase in terrestrial levels due to fallout. Radiation measurement sin residential dwellings in he New York metropolitan areas are described" (p. 1).

From Introduction: "In the following pages are summarized the factors which influence neutron economy and which, therefore, are important in nuclear safety."

This report summarizes the hazards associated with the operation of the Lynchburg Test Reactor (LTR) critical experiments. The LTR critical experiment program is outlined and the design of the experiment is described. The experiments will provide basic data to check two-dimensional calculational methods and provide information needed in the design of the LTR.

Technical report. From Abstract: "An ion exchange process was demonstrated for the recovery of Pu238 from irradiated neptunium oxide. Three cycles of anion exchange proved adequate for the removal of fission products and for the separation of the neptunium and plutonium from each other."

Technical report. From Abstract: "Ultrasonic energy appropriately applied to the die or container of a laboratory-type direct extrusion press effected a marked increase in the free extrusion rate of lead and aluminum billets at a constant extrusion rate. the same results were obtained in extrusion cladding steel tubes with aluminum. Rate increases were generally 100 per cent or greater, and decreases in force were usually within the range of 10 to 20 per cent. Furthermore, the shape and slope of the extrusion curves were altered. The effect appeared to be attributable to a reduction of both die friction and container wall friction under ultrasonic influence."

Technical report. From Abstract: "Rate data are presented for the oxidation of neptunium (V) by vanadium (V) in nitric acid." From Summary: "Rates of oxidation of neptunium (V) were determined by a solvent extraction technique based on the difference in distribution coefficients for neptunium (V) and neptunium (VI)."

Abstract: Critical experiment studies were performed, varying the parameters U235, B10 and metal to water ratio, in the SM-2 7 x 7 core configuration with 38 stationary elements and seven control rods of the SM-1 (APPR-1) type. An experimental mock-up of the SM-1 was assembled using the basic SM-2 fuel plates. Excellent agreement between the SM-1 boron loading, determined by chemical analysis, and the SM-1 mock-up boron loading, for equivalent bank positions, was noted. Several SM-2 mock-ups, cold clean and midlife, were assembled and studied with regard to reflector effects, flow divider effects, relative control rod array worths, critical rod configurations, and relative power distributions. The results of these experiments indicate as satisfactory a U235 loading of 36.4 Kg and a B10 loading of 63.4 grams for the SM-2. Attention is drawn to numerous power peaks present in the active core. The open seven control rod array has a slight reactivity advantage over the closed seven array and consequent minor disadvantage with respect to "stuck rod" criteria.

This study is concerned with a class of circuits which employs two tubes in a series connection--sometimes referred to as the stacked-tubes connection. This study will be concerned with two configurations that have shown considerable promise in the field of high speed circuitry. In Part I a configuration called the dynamic plate load amplifier is dealt with. In Part II a configuration called the White cathode follower is examined.

Report containing information regarding magnetic jacks, which are devices used "for positioning the control rods in a nuclear reactor, especially in a reactor containing water under pressure" (page 9). Contains a description of the device, its use, test results, and illustrations.