The object of this project is to conduct studies on the coating of metals and alloys by the gas plating process. Coatings to be studied consist of chromium on copper; alloys of nickel chromium on copper; molybdenum on stainless steel and Inconel; chromium on stainless steel and Inconel; and tungsten and molybdenum and their carbides on stainless steel and Inconel.

Monthly magazine discussing natural resources, parks, hunting and fishing, and other information related to the outdoors in Texas.

Annual report submitted by the Boy Scouts of America to Congress describing highlights from 1952, activities, finance, public relations, programming, organizational leadership, and other information about scouting programs.

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.

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.

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.

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.

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.

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

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.

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 supplement includes reports on (1) transmission measurements with the fast chopper, (2) a search for Pu244, (3) crystallographic studies, (4) resonance flux in CP-[gamma], (5) multigroup methods for concentrated fast assemblies, (6) work on the ZPR-1 Reactor, and (7) work on the ZPR-II Reactor.

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.

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.

A report regarding carnotite resources of the Moon Mesa and Horse Mesa Areas, Mesa Montrose Counties, Colorado.

A report regarding thorium resources located in the Mountain Pass District in San Bernadino County, California

A report regarding a reconnaissance performed in the Darby mountains District, the Seward Peninsula, Alaska, performed in order to locate radio deposits.

A report regarding the geology and mineralogy of the W. Wilson. Mine near Clancey, Jefferson County, Montana. This report concerns work done on behalf of the division of Raw Materials of the U.S. Atomic Energy Commission.

Interim report regarding an exploration of the Jo Dandy area, Montrose County, Colorado. Concerns work done on the behalf of the Division of Raw Materials of the U.S. Atomic Energy Commission.

An interim report regarding exploration of the Spring Creek Mesa Area, Montrose Country, Colorado. Concerns work done on behalf of the division of Raw Materials of the U.S. Atomic Energy Commission.

A report regarding uranium-bearing coal in the Red Desert, Great Divide Basin, Sweetwater County, Wyoming. Concerns work done on behalf of the Division of Raw Materials of the U.S. Atomic Energy Commission.

The accompanying map shows the results of an airborne radioactivity survey in an area of 800 square miles in Campbell and Johnson Counties, Wyoming.