"An apparatus using a silica Bourdon gage is described for the measurement of vapor pressures or dissociation pressures with an accuracy of 0.1 mm and 0.1 deg C up to maximum pressures of atmospheric or beyond and maximum temperatures of 650 to 1250 deg C. The method is applicable to corrosive substances, to substances whose vapor pressure is sensitive to slight changes in composition, and to substances difficult to purify of volatile contaminants which affect the vapor pressure."

"Expressions are found to relate DELTA gamma to the n-errors.'' It is demonstrated that the integral n-value concept'' is of no use in the present case. A modification of integrated n-value'' is suggested."

The general Wigner-Eisenbud theory is used to develop a method of analysis for the cross sections of fissionable nuclei. The method is employed in giving a reasonable description of the low energy cross sections in U/sup 235/. The single level fit for U/sup 235/ is known to be unreasonable. Many level expressions for the cross sections are derived--the only approximation to the general theory being the neglect of all but a small group of resonances. It is shown that regardless of the number or definition of the fission channels the many-level expressions require few level parameters: the E/sub lambda /, GAMMA / sub lambda n/, GAMMA /sub lambda gamma / and GAMMA /sub lambda F/ of the single level theory for each resonance and a few additional parameters pertinent to the interference between levels. The interference terms are described and shown to be important. The shape and size of the U/sup 235/ cross sections below 2 ev are fitied to within one per cent using (a) only one negative energy resonance of smaller size than in the single level fits (b) no additional levels to fit the shape other than the observed levels at positive energies (c) three interference parameters …

This technical report described the formulation of a set of two-group neutron diffusion equations and the solution for the critical fuel cross section in a one-dimensional, multi-region spherical reactor. A subsequent report will describe the ORACLE code developed for survey calculations using this method.

The dose of ionizing radiation received by passengers and crew members traveling on commercial airlines which transport radioisotopes is of interest to all persons who travel the airways frequently. Tariff regulations permit the air transport of 40 units of radioactive materials where one unit represents a quantity of radioisotopes which when packaged delivers a dose rate of one mr/hr at a distance of one meter from the center of the package. Using five different types of commercial aircraft, shipments of radioisotopes were simulated and dose levels determined at various locations in the aircraft under conditions normal to commercial travel. The survey indicates that the tariff regulations should be amended giving consideration to the type of aircraft involved.

An order of magnitude estimate was made to determine a minimum cost for 10% pure oxygen-17 when produced by a chemical exchange process. the calculations were based on separations factors of 1.03, 1.01, and 1.003. the cost of product was found to vary from $23 per gram for the large factor to $165 per gram for the smaller.

Recent measurements on the long counter efficiency in which comparisons were made with the (n, p) scattering cross section, additional variations in efficiency were found which varied slowly with neutron energy but were still correlated with the total neutron cross section of carbon. Because of these variations in efficiency there are errors in the fission cross sections reported in LA-1714. Corrections to these data have been given here.

Report discussing interactions of 420-Mev/c K- mesons incident on a nuclear emulsion stack. Information on the differential scattering, elastic scattering, absorption events, and inelastic scattering of the mesons is provided. Additionally, the ratio of Λ to Σ hyperons produced in the primary interaction is calculated.

"An experimental study has been made regarding the passage of a beam of 100-kV ions (H⁺ and H₂⁺) across a magnetic field by means of a crossed electric field." This experiment was designed to answer the following questions: "(1) Is there a limit to the current that will traverse a magnetic field by the action of a crossed electric field? If so, what is the limit? (2) Do difficulties arise in maintaining the electric field? (3) For the source employed, what is the angular divergence and current density of the beam?"

Abstract: "Experimental evidence is given which indicates that electronic bombardment is responsible for damage and failure of insulating material subjected to intense corona attack. The experimental revolts are further supported by some theoretical considerations of the energy-time properties of corona discharges."

Abstract: "A radioactive tracer, Fe^59, was used to determine the disposition of iron as a result of the excitation of a U3O8 matrix in a d - c arc. Two different spectrographic procedures, both using carrier distillation excitation techniques, were compared as to the percent of iron volatilized, the percent of iron diffused into the electrode and the percent of iron remaining in the residual charge."

A report about equipment which is assembled and tested to determine the feasibility of measuring the thermal conductivity and electrical resistivity of irradiated uranium rods clad with Zircaloy 2 with NaK as the heat-transfer medium.

A report which studies the feasibility of measuring the thermal conductivity and electrical resistivity of irradiated uranium rods clad with Zircaloy 2, with NaK as the heat-transfer medium.

A report which investigates the effect of irradiation on the thermal conductivity of uranium. Thermal-conductivity measurements are made on clad uranium specimens prior to irradiation.

A report about the design and construction of equipment for thermal-conductivity measurements of irradiated encapsulated uranium. Metallographic techniques used to confirm solubility limits of uranium in thorium, previously determined by electrical resistivity and X-ray data, have been unsuccessful.

A report about thermal conductivity measurements which are made on uranium, uranium-1.5 w/o zirconium, and zircaloy 2 for a program that aims to determine the feasibility of using clad specimens. Results from the measurements indicate that the difference in thermal conductivity values between uranium and uranium-1.5 w/o zirconium is less than the anticipated 5 percent.

A report about the effect of irradiation on the thermal conductivity of uranium.

A report about equipment being constructed to measure the thermal conductivity and electrical resistivity of irradiated uranium rods clad in Zircaloy 2, with NaK as the heat-transfer medium.

From abstract: This report describes a conceptual design for an Advanced Engineering Test Reactor. The reactor is a large graphite assembly penetrated by parallel Zircaloy tubes through which flow as heavy water solution of uranyl sulfate. Reactor power is 220 megawatts.

From abstract: The response of the reactor to forced oscillations has been investigated with the pile oscillator technique and the data are presently being analyzed.

This report covers a feasibility study for a 15 megawatt gas cooled reactor power system, conducted by the Ford Instrument Company Division of the Sperry Rand Corporation during the months of March to August 1956.

From introduction: The primary aim of this study is to present as complete a geologic picture as possible, of the Chattanooga shale in its outcrop area of the Eastern Highland Rim and the Northern Highland Rim of Tennessee and adjacent Kentucky. Special emphasis has been placed upon the stratigraphic relationships and their implications upon the age and manner of origin of the sediments and upon the origin, source, and distribution of uranium in the shale.

Design and operational techniques are described for a freeze seal type centifugal pump for use in the Sodium Reactor Experiment.

Report describing "the startup operation of a batch production facility for separating and purifying barium-140 from short-cooled MTR fuel" (p. 3).