Although the results reported herein are rather encouraging and show the possibilities of utilizing flotation to increase recoveries and in some instances grades, they should not not be considered an optimum. As stated previously, time did not permit a detailed investigation of all reagents an conditions to obtain maximum grades and recoveries, but sufficient data, with enough typical samples, have been obtained to indicate a definite trend and encouragement for further studies. A comparison of the flotation results obtained with each of the samples is presented in Table 2.

Abstract: The results indicated that increased reliability can be obtained by using thermocouples made with insulation of increased density and/or a low thermal expansion sheath.

Abstract: This report presents the pertinent results of a series of fatigue tests relating to the evaporator and superheater 37-tube module heads for the sodium heated steam generator described in NAA-SR-9826.

From introduction: "Studies were made of single crystals of thorium nitrate hydrate which we had available in this laboratory and from these we were able to determine the unit cell and find the thorium positions. These crystals contain on the order of six water molecules per thorium atom, but the exact composition is in some doubt."

The following report provides results taken from a sodium level indicator developed at Sacandaga using electrical resistance as the principle.

Single-point DOPTAP computer output files for all profile data for the map lines and tie lines surveyed in a report of aerial radiometric and magnetic survey of the Wichita, Texas area.

Averaged GEOL computer output files for all profile data for the map lines and tie lines surveyed in a report on aerial radiometric and magnetic survey in Oklahoma City, Oklahoma.

Averaged GEOL computer output files for all profile data for the map lines and tie lines surveyed in a report on aerial radiometric and magnetic survey in Oklahoma.

Averaged GEOL computer output files for all profile data for the map lines and tie lines surveyed in a report on aerial radiometric and magnetic survey in the Wichita Falls, Texas area.

Single-point DOPTAP computer output files for all profile data for the map lines and tie lines surveyed in a report of aerial radiometric and magnetic survey in Oklahoma.

Single-point DOPTAP computer output files for all profile data for the map lines and tie lines surveyed in a report of aerial radiometric and magnetic survey of Oklahoma City, Oklahoma.

Averaged GEOL computer output files for all profile data for the map lines and tie lines surveyed in a report on aerial radiometric and magnetic survey in Oklahoma and Texas.

Single-point DOPTAP computer output files for all profile data for the map lines and tie lines surveyed in a report of aerial radiometric and magnetic survey in Texas and Oklahoma.

Abstract: The yields of U²³⁷ and a fission product were measured as a function of maximum betatron energy, The ratio of the number of fissions divided by the number of U²³⁷ atoms increases with increasing maximum betatron energy. This is consistent with the picture that the higher-energy gammas leave the U²³⁷ atoms with enough excitation energy (above photofission and photoneutron thresholds) to also decay by fission or neutron emission. This secondary process increases the number of fissions and decreases the U²³⁷ yield, this increasing the above ratio.

Abstract: "UO2 and ThO2 form a continuous series of solid solutions with the solidus-liquidus from 2875 C for UO2 to above 3200 C for ThO2."

The following report provides the analysis of a large number of unreported data--taken during a study described in report HW-15230--containing density values obtained for solutions of uranium and nitric acid in tributyl phosphate-carbon tetrachloride solutions.

The purpose of this report is to present a method of impregnating beryllium oxide with uranium and to describe the properties of beryllium oxide and of commercial beryllium oxide ceramics.

Abstract: "The age-diffusion is adequate to describe the neutron behavior of a very large class of nonthermal reactors (all except those whose dimensions are comparable to the neutron mean free path). Thus, a convenient means of obtaining an accurate solution to this equation is very useful for general reactor calculations. Methods for reducing the age-diffusion equation to a finite set of coupled ordinary differential equations, called multigroup equations, are described. The relative merits of several alternate schemes are discussed. The multigroup equations may be solved by iterative procedures based on an assumed spatial distribution of the fission source neutrons. In practice the initially assumed source shape is accurate enough so that additional iterations are unnecessary. Analytical and numerical methods for solving the multigroup equations with the assumed source are discussed. The adjoint equations are also reduced to multigroup form, and examples of the adjoint function in obtaining improved reactivity values are given."

From introduction: "One of the most important factors which must be considered in the chemical processing of spent fuel elements is the safe and economic disposal of gaseous radioactive fission product wastes given off in the fuel element dissolution operation. For this reason work is underway at ORNL to study the various gas disposal methods that might be used to handle the radioactive fission product gases, krypton, xenon, and iodine."

The following report describes the usage of a semi-continuous ion exchange contactor--named the Higgins contactor--fit to operate the Purex process, a process that recovers plutonium and uranium from irradiated natural uranium fuel elements. It is intended to use the contactor in the final purification and concentration stage of the process plutonium streams.

This report was written to replace the directions submitted on April 12, 1943 with improved directions for the preparation of chemical solution X(OC₂H₅)₅.

"The purpose of this memo is to set down a derivation and numerical technique for a method that can be used for criticality calculations on bare reactors containing hydrogen together with another moderator such as BeO. The method and notation are that of G. Goertzel (NDA)-1, and D. Selengut (NEPA). In the interest of the computers, the numerical technique, associated notation, and calculation form are modeled after that currently used by the ANP Physics Group for BeO moderated reactors."

Abstract: "A series of experiments was carried out to determine the precision of the spectrochemical procedure for the isotopic analysis of uranium, especially at low uranium 235 concentrations. Standards were prepared from uranium hexafluoride which had been assayed on the mass spectrometer with a 95 per cent confidence interval of 0.5 per cent of the amount present. For a determination consisting of 9 separate measurements, the best precision obtained at normal concentration on the 95 per cent confidence interval was 0.711 +/- 0.112 per cent uranium 235 (16 per cent of the amount present)."

Abstract: "The Calutron has been successfully employed to separate the stable isotopes of twenty-one elements. The standard Beta M-2 unit modified to handle charge materials of various temperature ranges has proven adequate for a majority of separations. The problem of K life has received considerable attention but is still to be solved. Other operational problems are similar in most respects to those of uranium. The E design has, of necessity, varied greatly from the "Beta Gloria" type. A desire to keep construction simple, yet adequate for efficient collection and readily adaptable for use with many elements, has dictated the trend in E design. Water cooling on the receiver pockets was necessary with many of the elements separated. The chemical purification of the separated samples, although following a general pattern, varies with the type of pockets used and the element collected."