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Tabulated are critical masses of simple systems, which have been measured at Los Alamos through the year 1963

Annual report submitted by the Girl Scouts of the United States of America to Congress describing highlights from 1963, activities, services, public relations, finances, organizational leadership, and other information about scouting programs.

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A complete bibliography was assembled of Rover fuel processing and molten salt fluoride volatility processing research at, or sponsored by, Oak Ridge National Laboratory. The bibliography contains open literature references, topical reports, status and progress reports, and technical memoranda. (auth)

Budgets are presented for the following projects: plutonium recovery; plutonium reduction development; new products; plutonium--nuclear and chemical safety; and plutonium equipment and instrument development. Project scope and accomplishments are briefly described.

This report presents additional justification for operating costs of the Separations Research and Development Program which consists of eleven identifiable activities in four general areas of effort. The activities and their proposed levels of effort are listed. For each of the identifiable activities, the major accomplishments of the last year are listed, together with the proposed goals for the next two years, in the following pages. Significant trends in the program are noted.

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This report describes a test program which was conducted to determine whether the cold-flow (with Hsub2 gas) thermal characteristics of an NRX-type graphite reactor core can be simulated by a metal core during the transient period of the Cold-Flow Development Test Systems.

Five batches of pyrolytic-carbon-coated uranium carbide particles were exposed to partial pressures of water vapor ranging from 20 to 635 mm Hg at temperatures of 700 to 1100 deg C. All batches of coated particles had laminar type of coating and contained cores consisting principally of uranium dicarbide. The rate of reaction of the pyrolytic-carbon coatings with water vapor was determined from weight losses. The extent of failure of the coatings during exposure was established by microscopic examination and leaching of the particles with 8M HNO/sub 3/. Differences in the protectiveness of coatings present on the various batches of particles are attributable, at least in part, to two types of attack by water vapor, a localized or pitting type and a more general type. Rapid failure of the coatings was indicated at 1100 deg C. The coatings on some batches of particles remained protective at temperatures of 800 to 1000 deg C. (auth)

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The coolant-channel spacing between two flat fuel plates may be measured using an eddy-current induction coil. The range and sensitivity of these spacing measurements are functions of the coil geometry, the material surrounding the coil, and the operating frequency. Experimental curves are given showing how the coil impedance varies as a function of geometry, frequency, and the material surrounding the coil. A design problem is solved showing the compromises made between range and sensitivity which determine the coil geometry. The wire size and hence the proper number of turns are selected to match the coil to an alternating current bridge. Probe construction techniques are given to help the user construct both the coil and the apparatus to position the coil in the coolant channel. The necessary data for the design of spacing probes for many similar problems are given. (auth)

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The United States and the European Atomic Energy Community (Euratom), on May 29, and June 18, 1958, signed an agreement which provides a basis for co-operation in programs for the advancement of the peaceful applications of atomic energy. The work described in this report represents the Joint U.S.-Euratom effort. The over-all development program is designed to obtain the test data and operating experience necessary to eventually realize a 50 percent increase in the output of the Garigliano Nuclear Power Station located at Sessa Aurunca (Campania, Italy). Two tasks are in progress: Task III-F involves the preparation of test specimens of reactor vessel material for irradiation; Task IV consists of the formulation of specification for a complete data logging and computer system.

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