In the past it was felt that the easiest way to treat a three group equation for a MTA lattice was to solve it without certain terms. This iterative procedure converged rapidly for a medium with depleted uranium fuel, and in fact, a second iteration was not needed.

The energy distributions of neutrons in the 3-10 Mev energy range resulting from the bombardment of thin U targets are being investigated by the measurement of proton recoils in photographic plates.

The following report provides data that was discovered from a preliminary literature survey that was made to define the utility of the newer refractory ceramics or ceramic-based materials.

Abstract: The counting accuracy of the Chicago Scalers, Models 961A and 961B, is a function of the bias setting of the limiter (V2). this report gives quantitative data supporting this thesis. A method of making bias settings is suggested. These tests were run at the suggestion of Mr. V. C. Hanson.

The purpose of this note is to recalculate the semi-empirical curve of neutron yield vs. deuteron energy originally obtained by H. York in order to predict, using it and the best available data, what yields may be expected for deuterons on uranium in the extrapolated energy region.

From abstract: "Bis(di-n-hexylphosphinyl)methane, HDPM, [(C6H13)2P(O)]2CH2, has been studied as an extractant for a variety of metals. HDPM was evaluated as an extractant for uranium(VI) and compared with tri-n-octylphosphine oxide, TOPO, (C8H13)3PO. In nonpolar solvents, HDPM forms a polymeric-like substance with compounds of uranium(VI). Viscosity measurements indicate that the molecular weight of this polymeric-like substance is about 100 times greater than the corresponding complex with TOPO. Polymer formation occurs only when nonpolar solvents are used as diluents for HDPM and is easily avoided by using polar solvents such as 1,2-aichlorobenzene. HDPM forms 1:1 and 2:1 complexes with uranium(VI) nitrate. Equilibrium constants for these complexes as well as that for the 2:1 TOPO complex were calculated and it was shown that the over-all constant is at least ten times larger for the HDPM complex than for the TOPO complex. The effect of concentration of various mineral acids, extractant concentration, temperature, and diluents on the extraction of uranium are discussed."

Abstract: A core design study of a 10 Mwe fast ceramic reactor is presented. Local reactivity coefficients, safety criteria, accident analyses, and economics are considered. An attempt is made to find a new balance of characteristics by purely geometric devices, i.e., by exploring the sodium : fuel ratio and varying the height : diameter ratio of the core. The use of BeO in the core was also investigated.

Report describing the Hanford Laboratory controlled potential coulometer. This includes the theory behind the coulometer, details of its circuitry, and performance tests. Appendix begins on page 23.

Many measurement of neutron spectra have been made in water assemblies. In these system a large part of the spectrum is given by an essentially Maxwellian distribution at the moderator temperature which is insensitive to the scattering model. Hence, the test of the energy exchange scattering kernel is in the difference of the spectrum and the fundamental or Maxwellian component. The figure shows the spectrum for the Nelkin model. Once the fundamental has been subtracted neither theoretical model seems to fit the data extremely well. Below kT the Nelkin model is a closer fit than the gas model but it underestimates the deviation from the Maxwellian whereas in the joining region it overestimates the distortion.

Abstract: Pure UO2F2 is made by reaction between anhydrous HF and pure UO3. Although it is difficult to prepare free of water, it is not very hygroscopic. Prolonged heating at 100-105 degrees releases 99.9% of the water in an aqueous solution; the rate of loss of water is very small after saturation is reached. X-ray diffraction data give a density of 6.2 for the solid. The density of a 1.004 M solution is 1.274; the density of a saturated solution (5.130 M) is 2.400. The densities of F-9 solutions have been calculated from the densities of ordinary aqueous solutions, and the values are compared graphically. Data on the solubility indicate that there is a small increase in the range 25-100 degrees. Recovery of pure F-9 from a solution is hampered by hydrolysis of U)2F2 to give HF. The HF may be held back by addition of UO3 or CaO; the use of the latter, however, makes more difficult the recovery of all the F-9. Molar conductivities of UO2F2 solutions at 25 degrees, as well as the specific conductivities of a 1 molar solution containing various concentrations of UO3, have been determined. The addition of UO3 lowers the conductivity. The low …

From introduction: "In order to locate systematic trends of states with a certain angular momentum and parity Jπ in nuclei having constant neutron excess, both the ground state and the level energies will be considered simultaneously: we plot the total nuclear binding energy or nuclidic mass excess of excited states, whereby the ground states appear as a special case. Such a natural correlation of level schemes has been employed before Inglis already in 1953."

Abstract: A discussion of the potential hazards of chlorine trifluoride is presented and a series of safe handling procedures is recommended.

Summary: The Regnault Method as applied to tritium purity determinations is described. The operating difficulties, such as temperature and humidity changes, static charges, excessive vibrations, contamination with air and helium, etc., and the methods currently in use for minimizing such difficulties, are discussed. A discussion of ion-chamber calibrations, and the correlation of ion-chamber results with Regnault Method results, are included. A precision of ±1% has been obtained, but the accuracy is not yet known.

Abstract: This report presents the results of a study performed by the Ford Instrument Company, Division of Sperry Rand Corporation, and its subcontractor, Maryland Shipbuilding & Drydock Company, for the Maritime Administration, U. S. Department of Commerce, under terms of Study Contract No. MA-1893, dated March 11, 1959. The purpose of this study is to evaluate various techniques for pretesting and installing nuclear prototype power plants in merchant ships and develop that technique offering the widest general application using time, cost and safety as essential criteria. Acknowledgement is made for the valuable counsel received from personnel of the American Bureau of Shipping, Isbrandtsen Company, Inc., Maritime Administration, Atomic Energy Commission, and the United States Coast Guard.

Analysis that is fast and has extremely low levels of detection for more than forty elements that may be present in lead.

A method to determine the correction to Grüneisen's law corresponding to the effect of the electrons at high pressure. It is assumed that the lattice contribution to the pressure is small and that the equation of state of the solid can be approximated by results of the statistical Thomas-Fermi atom model for the electron pressure.

Abstract: The number of photons of given energy radiated in Bremsstrahlung collision of electrons with nuclei is calculated relativistically. Expansions are obtained for energies small to mc-squared. The photon spectrum is averaged over a Maxwell distribution for the electrons. Numerical results are included.

The purpose of this study has been to evaluate the chemical resistance of various bearing materials to solutions of nitric acid and uranyl nitrate hexahydrate with views toward selecting the best material to be used as bearings in Purex submerged rotating equipment.

Report presenting the properties and method of preparation of zirconium nitride, a compound that was being considered for use in high temperatures due to its high melting point and hardness.

The purpose of this paper is to describe a few of the suggested advanced concepts for fast breeder reactors and to compare these with the standard approach as to their potential advantage. I have attempted to estimate the economic effect of full technical success with each of the proposed concepts. The proposed concepts include: (1) single sodium system, (2) steam-cooled core concept, (3) direct cycle reactor using potassium as reactor coolant and working fluid, (4) molten plutonium-fuel alloy circulated and cooled by a jet of sodium, (5) settled-bed core, (6) molten salt concept, and (7) paste-fuel system.

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.

The results of analyses of the airborne gamma radiation and total magnetic field survey flown for the region identified as the Trona National Topographic Map NI-11-12 is presented in Volume I and II of this report. This volume gives the description of the program and the results.

Average record data listings taken during aerial gamma-ray and magnetic surveys of the Trona quadrangle in California.

Single record data listings taken during aerial gamma-ray and magnetic surveys of the Trona quadrangle in California.