Description of the Oceanographic Project and the results of the 1950 Winter Cruise of the Hugh M. Smith.

Report issued by the U.S. Bureau of Mines on the motor fuel sold in the U.S. during the winter of 1950-1951. Analysis of properties and trend characteristics of the fuel samples are presented. This report includes tables, graphs, and a map.

Report issued by the U.S. Bureau of Mines on the oil-shale operations at New South Wales, Australia in 1947. The methods, and types of equipment used are presented. The report includes maps, photographs, and illustrations of the oil-shale refinery.

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This report presents data on the absorption of tritium oxide vapor through human skin.

Report issued by the U.S. Bureau of Mines discussing the petroleum refineries in the United States during 1951. Locations and crude-oil capacities of the refineries are presented. This report includes tables, and a map.

Technical report covering classified work of the Critical Experiments Program in the Physics Division for the period December 20, 1950 to March 20, 1951. Report outlines investigations of properties of critical assemblies composed of uranium and various reflectors and moderators, preliminary measurements of the effective energy for fission in the assembly. [From Introduction and Summary]

The power output of the piles is being restricted primarily by three important limitations; those due to graphite temperatures, slug and tube corrosion and maximum power per tube or ``boiling disease.`` The purpose of this document is to present means for increasing very appreciably the ``boiling disease`` limits. In addition, means for alleviating the corrosion limitations will be discussed.

"A light-source power unit has been developed that provides reliable trigger, and easy synchronization with rotating elements or electric impulses. When used with conventional spark gaps and flash tubes, this power unit provides a light pulse of high intensity and short duration" (p. 1).

Note presenting an investigation of the instability of flow from two ducts that join into a common duct and of the influence of the various parameters on the phenomenon. A two-dimensional potential analysis was carried out under the assumption that the two ducts discharge into a region of constant pressure.

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The volume of H/sub 2/ evolved on dissolving screened nonroasted U- bearing scrap, slag, and liner in HCl were determined; the values were found to indicate the degree of removal of metallic particles by screening. Digestions of nonroasted plant-pulverized scrap with HNO/sub 3/, NaNO/sub 3/, or Fe/sub 2/(SO/ sub 4/)/sub 3/ in HCl and with HNO/sub 3/ or NaNO/sub 3/ in H/su b 2/SO/sub 4/ were not so effective as digestion with NaClO/sub 3/ in HCl. Doubling the free acid content and addition of FeSO/sub 4/ improved the efficiency of the latter digestion. Removal of CaF/sub 2/ from crude (NH/sub 4/)/sub 2/ UO/sub 4/ by solution of the uranate in acetic acid, HCl, or Hsub 2SO/sub 4/ was limited by slow filtration rates. (W.L.H.)

The study of radiation damage to the graphite moderator is largely dependent upon the availability of graphite samples from the moderator itself. Because of the varied temperature-flux history and complicated structure of the piles, it is impossible to study the problem from the laboratory standpoint alone. The samples of greatest interest are those taken from the sections of the moderator which have received the greatest damage. However, a comprehensive study requires samples from all sections of the graphite moderator. It is desirable that these samples be solid in order that physical and dimensional measurements of all types may be made. Solid samples enable thermal conductivity measurements and the gradients of damage across tube blocks to be measured. To provide such samples, it was necessary to design some device which would cut solid samples from any location in the pile through the process Channels. The graphite core borer was desigred specifically for this purpose. The objective of this Production Test was to test the operation of the core barer and evaluate the results of its performance.

Abstract: An evaluation is made of radioactivity logging as applied to exploration drilling on the Colorado Plateau. The compilation of data gives a preliminary insight into the possibilities of the technique being applied.

Project C-431-A includes the design of the C Water Plant outfall structure. This report documents design assumptions and the design of the spillway, outfall sewers, spillway chute, trash racks, walkways, stop log and trash rack slots, main sewer, and retention sewers. The spillway capacity is to be 268,000 gpm with a crest elevation at 429.0. This flow capacity is composed of flow from the 105-C Retention Basin (80,000 gpm), 105-B Retention Basin (45,000 gpm), and the 190-C Area main sewer (143,000 gpm).

Report presenting the development of a rapid approximate method of analysis for both compressible and incompressible, nonviscous flow through radial- or mixed-flow centrifugal compressors with arbitrary hub and shroud contours and arbitrary blade shape. The method is used with eight numerical examples for two-dimensional flow, covering a wide range of flow rate, impeller-tip speed, number of blades, and blade curvature.

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"When porcelain enamels or vitreous-type ceramic coatings are applied to ferrous metals, there is believed to be an evolution of hydrogen gas both during and after the firing operation. At elevated temperatures rapid evolution may result in blistering while if hydrogen becomes trapped in the steel during the rapid cooling following the firing operation gas pressures may be generated at the coating-metal interface and flakes of the coating literally blown off the metal. To determine experimentally the relative importance of the principal sources of the hydrogen causing the defects, a procedure was devised in which heavy hydrogen (deuterium) was substituted in turn for regular hydrogen in each of five possible hydrogen-producing operations in the coating process" (p. 269).

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The 105-B Pile which was shut down on July 18, 1951 to permit removal of a ruptured uranium slug from tube No. 2169-B. The rupture was detected from effluent water monitor evidence and a survey of rear face pigtails. Removal was accomplished with the pneumatic charging machine using only normal pushing force.