Abstract: "The general utility of vacuum evaporated films is discussed. The characteristics that makes this technique most useful are the uniformity of the films, the easy control of their thickness over a large range, and the adaptability of the system to different metals and compounds. The design of a vacuum evaporator should provide adequate pumping speed, cooling of components, filament heater supply, and general flexibility and adaptability of the components to different materials. The design of filaments or boats and the evaporation of Al, Ag, Au, Li, Na, UCl4, ThF4, Be, SiO, Nal (Tl), U, and UO2 are considered. Special attention is given to the problem of obtaining uniform layers of UO2 on a large, flat target relatively close to the source."

From abstract: "The stability of polystyrene and phenolic ion-exchange resins to radiation from a Co60 source and from absorbed Ce144-PR144 was investigated. Sulfonated polystyrene cation-exchange resins lost 10 to 20% of their capacity per watt-hour of radiation absorbed per gram of oven-dry resin, while the quaternary amine anion-exchange polystyrene resins lost about 40%. Phenolic cation-exchange resins lost only 1%."

Report discussing the procedures and experimental data of various plutonium waste recovery methods. The report elaborates on the different methods of collection necessary for different wastes.

From summary: The object of the study was to determine if the heavy metal ions within the concentration ranges normally found in pile cooling water were responsible for corrosion of aluminum.

Introduction: "The problem of determining the properties and necessary controls on the TBP Plant waste disposal to eliminate transport line plugging and to permit higher concentration prior to return of this to the tank farms was studied. A report of preliminary findings was made to L. W. Finsh on January 31, 1953. This report compiles information in the aforementioned report and findings since its issuance. Previous studies related to this problem are summarized in the U. R. Technical Manual, HW-19140."

Abstract: "Laboratory production of an explosion between UNH and "red oil" under calcination conditions has been accomplished. Attempted production of a vapor phase explosion was unsuccessful below 150-160 C. Since such severe conditions are necessary to obtain an explosive reaction, it appears that present Purex plant design is adequate to avoid explosive conditions."

Introduction: "In the evaluation of pile designs it is necessary to know how the production varies with the number of tubes. It has been possible to solve the problem in terms of some general parameters whose values may be quickly computed for any specific design when the pertinent information is available."

Report discussing the distribution of mass in the spontaneous fission of Cm²⁴², which was investigated by a radiochemical determination of the fission yields of twenty-one nuclides ranging in mass from 91 to 140. "Corrections for absorption, scattering, geometry, decay, and fractional saturation were applied to obtain saturation disintegration rates, which, with the known fission rate of the source, give the fission yields."

Abstract: "In a circulating-fuel reactor, the circulation of the fuel cause a damping of power oscillations of the reactor. This is demonstrated under the assumption, that there is no mechanical vibration coupled with the oscillation of reactor power, and that the shapes of the hydrodynamic flow does not vary with time."

Abstract: "The reaction between nitrogen and carbon dioxide, under irradiation with 40 Mev alpha particles from the Berkeley 60 inch cyclotron, was studied at gas temperatures near 50 C and total pressures of about 600 millimeters of Hg, contained in Pyrex capsules. The range of gas compositions investigated included the pure components, as well as mixtures with and without trace oxygen. In all mixtures, a steady state concentration of nitrogen oxides of about 0.15 millimeter was reached after a few microampere hours exposure. The mass-spectrometer analytical procedure employed did not permit identification of the individual species of oxides present. This report is based on studies conducted for the Atomic Energy Commission under Contract AT-11-1-GEN-8."

Abstract: "A description of the demand computer and its functions is given. Methods of testing and adjusting, and gain and response curves for the system and its parts are included."

The susceptibleness of certain "ceramic" substances to extreme radiation damage (such as that observed in graphite) as indicated by changes in dimensions and heat content is discussed in terms of the experimental evidence which is available.

The use of bromine trifluoride solution has been investigated for the preparation of purified uranium hexafluoride from ore concentrates. The best yields were obtained with the use of antimony pentafluoride solutions in bromine trifluoride, and less fluorine was consumed in the case of previously hydro fluorinated samples. This approach appears to be technologically sound and may prove economically superior to existing procedures in the case of newly constructed facilities.

The cup assembly of the Experimental Breeder Reactor (EBR) consists of blanket bricks, inner rings, and safety plug, all of natural uranium. The design of the finish machined brick is shown in Figure 1. These pie shaped bricks when stacked together, 12 bricks arranged in circular form and stacked seven rings high, comprise the cylindrical portion of the outer blanket, 17.875" I.D. x 30.875" O.D. after machining and canning. The inner ring, which is shown in Figure 2, fits inside the bottom layer of bricks. The circular opening in the center of the inner ring is closed by the safety plug shown in Figure 3.

Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, research, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.

This report is a summary of the neutron attenuation data which have been obtained at the Brookhaven shielding facility on a mock-up of the fuel-rod-unloading plug used in the KAPL Reactor. Before this program was initiated, a number of small scale tests had been made in the ORNL lid tank on carbon steel mock-ups of components of the rotating plug. The results of the tests indicated considerable neutron streaming through the vertical steel and air members of the plug. However, the lid tank source strength and dimensions did not permit the tests to be extended to the full plug height. In view of the concern aroused by the ORNL tests and the absence of fundamental information on the transmission of neutrons through steel and the addition height (12') available here resulted in a request for BNL to construct and test a mock-up of a sector of the SIR top plug in accordance with KAPL specifications.

A report about several lectures made at the mathematics panel.

It has been found that two silver atoms replace one polonium ion during the electrochemical exchange of polonium ion with silver metal. It is believed that the most probable exchange reaction may be described by the equation Po++ + 2Ag = Po + 2Ag+ . From the concentrations of polonium ion and Ag+ ion when the exchange reactions were terminated, calculations indicate Po = Po^ + 2e", E°< - 0.7.

Energy determinations have been made using the conversion and photo electron spectra and scintillation crystal pulse height analysis for twelve y-rays associated with the Rb82 decay (6.3 hours, B+, K-capture). The B+ spectrum is found to contain four allowed components of maximum energies 1080, 890, 610 and 300 kev. A tentative decay scheme is suggested.

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.

Report on UCRL progress in general physics research and accelerator operation and development.

The following report concerns the application of a relaxation mesh method for the determination of the average flux within the moderator of a light water moderated, 1.027 per cent U-235, hexagonal lattice with a volume ratio (V_H2O + V_Al)/V_Uranium of 4:1. It was hoped that the calculation would enable one to determine any differences in flux which might result from the fact that the unit cell is a hexagon instead of a cylinder. Because we were primarily interested in the effect due to geometry we applied the same theory, diffusion theory, to the hexagon by means of the mesh method and to the equivalent cylinder.

In the course of recovering uranium from Rand cyanide residues, large volumes of barren acid liquors are produced. With the flowsheets now under consideration it is not advisable to recycle such liquors and they are to be discarded. Consideration was given to the removal of manganese under conditions that would permit its recovery as MnO2.

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.