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The thermal cycling, irradiation behavior, and fabrication characteristics of U are strongly dependent upon grain size; a smaller grain size yields the better properties. Grain refinement of cast U may be accomplished either by hot working in the high alpha temperature range or by heat treatment; refinement by the latter method was the object of this investigation. The variables studied were time, temperature, specimen size, multiple quenching, and alphaannealing after quenching. The results of the investigation have led to the following conclusions, within the scope of the experimental conditions. The grain size of cast U may be appreciably refined by beta-quenching. Time and temperature in the beta phase are not significant in determining the final alpha grain size. Multiple beta-quenches (two to four times) produce better grain size refinement than a single quench. Alpha-annealing after beta-quenching causes recrystallization, but does not greatly affect the grain size. Gamma-quenching is not recommended as a practical heat treatment. (auth)

The design and operation of a calorimeter for use in the temperature range 1.8 to 4.2 deg K are presented, and the methods used in the treatment of data and calculation of results are discussed. The heat capacities of several Na- W bronzes (Na/sub x/WO/sub 3/) were determined in the temperature interval 1.8 to 4.2 deg K. Samples having x equal to 0.89, heat capacities are described adequately by the sum of two terms, one linear and one cubic in temperature. The electronic specific heat of each sample is obtained by evaluating the coefficient of the linear term, and the Rebye eharacteristic temperature derived from the coefficient of the cubic term. Rensities of one-electron energy levels at the Fermi energy, and effective electronic masses are calculated from the electronic specific heats. A plot of the density of states as a function of energy can be made if it is assumed that this curve is independent of Na concentration. The justification of this assumption is discussed in the light of current theories of the solid state. The density of states curve rises rapidly at higher energies, and this rise is interpreted in terms of the filling of a Brillouin zone or …

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This bibliography is a compilation of reports on production tests performed in the 300 Area from May 1944 to February 1957. It includes all tests covering engineering and physics experiments in the Hanford Test Reactor development; fabrication and subsequent irradiation of fuel elements and melt plant (slug fabrication) procedures. Subject, author and report number indexes are included. Addendum 1 gives the reactor production test number under which the fuel elements were irradiated.

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This is a revision of the Reactor Safety Bibliography prepared for the Reactor Safety Conference held at New York City on Oct. 31, 1957. It is not an exhaustive review of the published material on reactor safety but includes 223 selections from reports and published literature as a guide to some of the more recent and relevant material. (J.E.D.)

The present facilities at the University of Michigan for research in nuclear chemistry are described. The determination of the cross sections of various (d, alpha ) reactions induced by thc 7.78 plus or minus 0.05 Mev deuterons from the Unlversity of Michigan cyclotron is presented. The work on the absolute (d, alpha ) reaction cross sections has been simed at surveying the reaction yields as a function of atomic number with the hope of establishlng the presence or absence of closed shell effects in these values. Methods are presented for the separation of carrier free P, Se, Mn, Co, Y, and Nb. Work continued on the development and evaluation of radiochemical separatlon procedures for Ba, Sr, Ca, Ag. and In. A series of small-scale laboratory tests was conducted to determine the feasibility of the decontamination of I/sup 131/ from air by means of adsorption on a highly efflcient solid adsorber molecular sieve. Graphs are presented of atomic cross sections for thermal neutron activation of isotopes not found in nature vs. half life of daughter radioisotopes produced. (For preceding period see AECU-5575.) (W.L.H.)

An investigation of the inelastic and elastic reactions between high- energy neutrons nnd He nuclei was conducted with a cloud chamber filled with He and operating in a pulsed magnetic field of 21,700 gauss. Neutrons produced by bombardment of a 1/2-in. LiD target with 340-Mev protons in the 184-in. synchrocyclotron were collimated and passed through the 22-inch expansion cloud chamber, which was filled with He gas to a total pressure of 89.8 cm Hg. Exclusive of meson-producing reactions, the possible reactions are: Inelastic, He/ sup 4/(n,pn)t, He/sup 4/(n,d)t, He/sup 4/(n,2np)d, He/sup 4/(n, dn)d, He/sup 4/ (n,2n2p) n, He/sup 4/(n, 2n) He/s up 3/; and Elastic, He/sup 4/(n,n)He/sup 4/. The total number of events, for incident neutrons above 160 Mev, was normalized to the interpolated n-He/sup 4/ total cross section at 300 Mev, and absolute cross sections for the various processes were established. Energy and angular distributions of the reaction products were compared with available theoretical predictions and other experiments. A few cases of meson production were noted. (auth)

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Thirty-seven sterile materials of common construction usage, common lubricants, and samples of wearing apparel were injected as finely divided particles into the subcutaneous soft tissues of guinea pigs, each in six different sites. At intervals of 3, 7, 14, 21, 30, 65, or 90 days, an inoculation site of each material was excised, in toto, fixed, and examined microscopically. In addition, ten selected materials were injected into the liver and spleen and deposited on the omentum and mesentery of four guinea pigs for each material type. At intervals of 7, 14, 21, and 30 days, one of each group of four animals was sacrificed and a block of tissue containing the inoculum was removed from the tissues and organs, fixed, and examined histologically. The majority of materials induced only a mild and delayed inflammatory response followed by encapsulation at the end of 14 days and a relatively inert fibrous nodule produced by the 2lst or 30th day. Copper particles incited a marked inflammatory response with abscess formation which persisted until the 90th day, although showing signs of subsiding at this time. Cudmium lesions were characterized by a peculiar zone of necrosis about the particle aggregate which persisted until the 60th …

Progress is reported in studies directed toward an understanding of the mechanism of control of red blood cell formation. A relatively rapid and sensitive method of assay for erythropoietin was developed, using the rate of incorporation of iron-59 into the red cells of normal, hypophysectomized, or starved rats as a measure of the rate of erythropoiesis. Factors that control erythropoiesis through control of production of erythropoietin were studied. The effect of erythropoietin in initiating marrow activity was demonstrated in mice having a completely suppressed marrow as far as red cell formation is concerned. Data are reported from studies on the effect of cobalt in polycythemia, the site of erythropoietin production, the clinical significance of erythropoietin, the production of erythropoietin by fetuses in utero, the effect of erythropoietin on iron absorption, and the properties of erythropoietin isolated from plasma. A list of publications during the period is included. (C.H.)

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This document details activities of the Irradiation Processing Department during the month of November, 1957. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.

The proposed Yankee Atomic Electric Company Reactor is a pressurized light water reactor plant designed to produce ultimate1y 492 Mw of heat and 134 Mw of net electrical generation at full power. The initial core to be operated in the reactor is designed to produce 392 Mw of heat at full power which provides approximately 110 Mw of net electrical generation. The reactor is fueled with slightly enriched uranium dioxide UO/sub 2/, in the form of pressed and sintered 0.3 in. diameter cylindrical compacts stacked in 0.336 in. OD full length stainless steel tubes in a core 7.5 ft. in height. The reactor is cooled and moderated by light water. The design is subject to change in detail before manufacture. Design characteristics and reactor safeguard considerations are described. (C.H.)

This document details activities of the Irradiation Processing Department for the month of February 1957. (FI)