Data were obtained in non-flowing and flowing (continuous) batch adsorption systems to serve as a guide to the operating conditions that should be used in a resin-in-pulp adsorption system for the recovery of uranium from ores.

In a section of the area occupied by the Atomic Energy Commission in Grand Junction, Colorado, a pilot plant is being erected to test a resin-in-pulp process. The process is based on the adsorption of uranium by resin from acid pulps. The first ores to be treated at this plant will be Monticello Stockpile Material. Samples of the various stockpiles sere subjected to a series of leaching, filtering and settling tests, the results of which are presented in this report.

The attenuation curve of the deuterons stripped from He3 has been measured with a Faraday cup. The corresponding curve at 190 Mev was fit by assuming that the deuterons were monoenergetic, with three processes taking place.

At high excitation energies, competition of proton and c-particle emission with neutron emission becomes important. For low excitation, the competition between Y-emission, neutron emission, and fission should be taken into account. To aid in the evaluation of this competition an experiment has been performed to measure the number and energy spectrum of the protons and c-particles emitted in the high energy bombardment of uranium with protons, deuterons, and c-particles.

A theoretical study of the kinetics of a model of the Los Alamos Power Reactor Experiment (LAPRE) was made through integration of the dynamic equations with the IBM 701 computer. The stability is investigated under various conditions of power demand, rod-induced reactivity changes, and other conditions especially applicable to LAPRE. The results are given in graphical form, along with conclusions as to appropriate conditions of operation.

A high-vacuum casting furnace with an internal diameter of 15 inches has been designed, fabricated, and installed at LASL. The furnace was designed to accommodate casting crucibles up to 7 inches OD; however with a larger diameter heating element, casting crucibles up to 9 inches could be accommodated. This report describes the basic features of the furnace and presents engineering drawings of both the furnace and the furnace box.

Abstract: "The effect of heat treatment of 2000 to 4650 F on the structure of carbons from several sources have been investigated, using X-ray diffraction. Of particular interest was the effect of temperature on the degree of graphitization. The process of graphitization results in a larger graphite crystallite size in the ao direction, the plane of the layers, than in the co direction. No correlation was found between the structure of the coke heated at 2000 F and the degree of graphitization attained at 4650 F. Materials coked in a closed retort yielded a more perfect graphite structure than the same material coked with access to air. Carbon blacks yield graphite with a greater co lattice constant than cokes with comparable crystallite sizes."

From introduction: This is the first in a series of reports describing an investigation of the chemistry of uranium(VI) orthophosphate solutions which is at present underway in this laboratory. Spectrophotometric, potentiometric and solubility studies have been carried out, and it is the first of these which is reported here.

A set of 69 pile yield curves for the production of plutonium, americium, and curium isotopes in a neutron flux of 5 x 10<sup>14 cm<sup>-2 sec<sup>-1 is given. The differential analyzer of the University of California Radiation Laboratory was used in obtaining the curves. The curves are given also on log-log plots for comparison.

Abstract: "The cross section for the formation of Be⁷ from oxygen irradiated with high energy deuterons has been determined. The values are 4.5 millibarns at 100 Mev, 5.6 millibarns at 150 Mev, and 5.5 millibarns at 190 Mev."

Abstract: "The protection of thorium in hot water was studied. Copper electrocladding on thorium offers promising protection against hot water. The corrosion of thorium in 95 C water was reduced appreciably by a thorium phosphate film. The results of this abbreviated investigation offer a basis for the development of a method of protecting thorium at elevated temperatures in corrosive media."

A report which describes a variety of methods for processing a low-grade sulfide concentrate from the Congo. This concentrate consists primarily of sulfides of cobalt, nickel, and iron, plus about 10 percent uranium, present principally as uraninite.

Semi-empirical modifications of age theory have been made to interpret the critical masses of proton moderated assemblies, which may or may not have reflectors of various substances, in particular, water or steel. Section I shows that critical masses of untamped water moderated systems can be calculated by use of an appropriate age and linear extrapolation length. Assuming that all captures and fissions take place at thermal, a familiar expression can be set up which contains the age and extrapolation length which are not well determined by theory. An age value suggested by theory, (Sec. II) is taken and ORNL criticality data (K343) are used to find the best extrapolation length. With these values the K343 critical mases can be computed to bout +-5%, which is their estimated experimental uncertainty; this for H/U-235 atomic ratios between 43 and 755. Section II contains a theoretical discussion of effects which the simple "theory" of Sec I neglects. It is indicated that several of these effects compensate to make a simple theory more useful than one would believe at first sight. to take into account reflectors of water, water shield by cadmium, or steel of various thicknesses, it proves sufficient to alter the extrapolation …

A criticality equation is derived assuming slowing-down only by hydrogen. The use of criticality experiments as a basis for calculation is described. Approximate methods are given for handling inharmonicities and multi-region reactors. Some criticality data on solutions of U03 dissolved in H3PO4 are listed in Appendix 1, and the Goertzel-Selengut equations are derived in Appendix II.

Introduction: "In connection with conducting neutron experiments in a pit with earth and concrete walls, it was proposed that the background flux of neutrons might be reduced by lining the walls of the pit with a neutron absorber such as boron. To determine how much liner material would be desirable and what diminution in the neutron background could be expected, the following measurements were undertaken."

Abstract: "The NYX testing of the component disassembly equipment comprised repeated operation of both the quatrefoil disassembly machine and the foil press and shear to evaluate the suitability of these machines to perform their design function with reliability and convenience of operation. During testing, both design and operational deficiencies were found and corrected in the NYX equipment. In general, both machines operated satisfactorily after modification."

The following report provides tables that measure the pressure of hydrogen fluoride at given temperatures and the hydrolysis of uranium tetrafluoride.

Initial rough measurements of the quality of the gamma radiation from Co-60 in air indicated agreement with the theoretical calculations of Spencer and Fano for an infinite water medium. Further experiments were performed, duplicating the conditions assumed in the calculations. Since the spectral region between 100 kev and 1 mev has already been examined by Hayward, it was decided to investigate in detail the region below 100 kev and above 1.0 mev. Total radiation dosage measurements were made in water using Victoreen ion chambers. The build-up factor was measured as a function of distance. Good agreement was obtained with the results of White. The spectrum below 150 kev was examined with a small NaI(Tl) scintillation counter and both the shape of the spectrum and the attenuation as a function of distance was in good agreement with the calculations. At distance less than 30 cm from the source the spectral shape changed, gradually broadening with the peak shifting to higher energies. The primary region above 1.0 mev was examined using a large NaI(Tl) crystal, and the gradual loss of resolution in the two primaries as a function of distance with an increase in lower energy events was shown. The measurements to …

Bismuth metal was irradiated with 340 Mev protons in the circulating beam of the 184-inch Berkeley cyclotron. Nuclides formed as fission products during the course of the bombardment were separated and studied through the use of radiochemical techniques.

The excitation function for the reaction T3 (p, y) He4 has been extended to proton energies of 7.3 Mev. No experimental evidence is found for a resonance in the reaction up to this energy of bombarding protons.

Numerous articles have recently been published on nuclear pulse height analyses. This report describes an approach to the problem using existing scaling equipment (scale of 1024) as building blocks in a multi-channel pulse height analyzer.

Supplement to Progress Report on Flotation of Uranium Bearing Materials From Lake Athabaska Ore, Sample 43-1 that includes information on uranium lost in solution during flotation in an acid circuit.

At the request of the Atomic Energy Commission, a 456 pound sample of Lake Athabaska ore was shipped to this laboratory by the Radioactivity Division of the Canadian Bureau of Mines. The sample was received on March 10, 1952 and given our number 43-1. Several series of flotation tests were performed on the sample.

A report about copper-based cladding alloys and the alloying reactions based on these metals. Experiments are done to minimize the risk of melting extrusion billets.