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  Partner: UNT Libraries Government Documents Department
 Decade: 1940-1949
Monthly Progress Report No. 61 for May, 1948

Monthly Progress Report No. 61 for May, 1948

Date: May 31, 1948
Creator: Authors, Various
Description: This is the University of California, Radiation Laboratory monthly progress report for May 1948. It discusses the following: (1) 184-inch Cyclotron Program; (2) 60-inch Cyclotron Program; (3) Synchrotron Program; (4) Linear Accelerator Program; (5) Experimental Physics; (6) Theoretical Physics, (7) Isotope Separation Program; (8) Chemistry Departments; (9) Medical Physics; and (10) Health Physics and Chemistry.
Contributing Partner: UNT Libraries Government Documents Department
The Isolation and Properties of Curium

The Isolation and Properties of Curium

Date: August 1, 1948
Creator: Werner, Louis B.
Description: The isolation of curium, element number 96, in relatively pure form has been accomplished. A method, involving a solvent extraction process, is given for the purification of americium from lanthanum and other ions. The discovery of a higher oxidation state of americium led to a method of separating americium from curium. Separation of the two elements was also accomplished by use of ion exchange resins. The details of the isolation of curium are given; the results of the spectrographic analysis, specific activity measurement, and calorimetric determination of half life showed the curium to be relatively pure. The absorption of light of various wave-lengths by an aqueous solution of Cm(III) is described, and some physical effects of the radiation from the curium are noted.
Contributing Partner: UNT Libraries Government Documents Department
Isolation and Propterties of Curium

Isolation and Propterties of Curium

Date: July 28, 1948
Creator: Werner, L.B. & Perlman, I.
Description: The isolation of curium, element number 96, in relatively pure form has been accomplished. A method, involving a solvent extraction process, is given for the purification of americium from lanthanum and other ions. The discovery of a higher oxidation state of americium led to a method of separating americium from curium. Separation of the two elements was also accomplished by use of ion exchange resins. The details of the isolation of curium are given; the results of the spectrographic analysis, specific activity measurement, and calorimetric determination of half life showed the curium to be relatively pure. The absorption of light of various wave-lengths by an aqueous solution of Cm(III) is described, and some physical effects of the radiation from the curium are noted.
Contributing Partner: UNT Libraries Government Documents Department
Progress Report No. 63 June 15-July 15, 1948

Progress Report No. 63 June 15-July 15, 1948

Date: July 30, 1948
Creator: Authors, Various
Description: This is the University of California, Radiation Laboratory progress report for June 15-July 15, 1948. It discusses the following: (1) 184-inch Cyclotron Program; (2) 60-inch Cyclotron Program; (3) Synchrotron Program; (4) Linear Accelerator Program; (5) Experimental Physics; (6) Theoretical Physics, (7) Isotope Separation Program; (8) Chemistry Departments; (9) Medical Physics; and (10) Health Physics and Chemistry.
Contributing Partner: UNT Libraries Government Documents Department
Treatment of Torbernite

Treatment of Torbernite

Date: January 21, 1946
Creator: Brimm, E. O., Dr.
Description: Production of black oxide from torbernite was studied on a laboratory scale from the standpoint of uranium extraction, reagent requirements, and removal of impurities. A small portion of the material was examined for its mineral constituents, using optical properties, X-ray diffraction patterns, and chemical analysis for identification. About 50% of the material was quartz; 30% green crystals of a copper-uranium phosphate; 10% of a black mineral, which was not identified, but which appeared to be an oxide mixture of nickel, cobalt, copper, and molybdenum; and small amounts of gibbsite, laterite and feldspar. There were no lower oxides of uranium in the sample.
Contributing Partner: UNT Libraries Government Documents Department
Uranium Peroxide

Uranium Peroxide

Date: April 14, 1947
Creator: Brimm, E. O., Dr. & Nohr, P.
Description: It was desired to investigate the precipitation of UO{sub 4} in acid solution, in order to determine the suitability of this reaction for use in the purification of uranium. A series of tests was performed to establish the conditions for precipitation of UO{sub 4}. It was found that uranium could be completely precipitated from pure uranyl sulfate solution at a pH of 2.5 to 3.5, with only silght excess of H{sub 2}O{sub 2}. The presence of sodium sulfate interferred with complete precipitation. It was established that vanadium was preferentially oxidized, when present.
Contributing Partner: UNT Libraries Government Documents Department
The Site B Foundry (Final Report on Part I of P.A. No. 151-ML-54-2, F.S. 41)

The Site B Foundry (Final Report on Part I of P.A. No. 151-ML-54-2, F.S. 41)

Date: February 12, 1945
Creator: Lauletta, Paul
Description: The Site B Foundry is equipped for the melting and casting of tuballoy and its alloys. Castings weighing up to 750 pounds and as long as 40 inches can be made. Melting can be carried out in the vacuum, in inert gases or under fluxes. Heating is by high frequency induction. A description of the generally foundry layout, the furnace construction and operation, and of the auxiliary equipment is given in this report. The casting technique used in the Site B Foundry is designed to minimize piping and cold shuts in the billets. The top of the mold is kept hot and freezing of the billet takes place from the bottom. This hot topping minimizes piping. Controlled pouring into warm molds minimized cold shuts.
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A Study of the Distribution of Impurities in the Extraction of Uranyl Nitrate with Ether from Aqueous Solutions

A Study of the Distribution of Impurities in the Extraction of Uranyl Nitrate with Ether from Aqueous Solutions

Date: April 1, 1946
Creator: Conard, C. R.
Description: Early in 1942 it had been found on a laboratory scale that certain impurities such as the Rare Earths were removed by small water washes from an ether solution of Uranyl Nitrate. It was hoped that in the large production units to be constructed that the water soluble impurities would all be washed out by the time the radioactive Thorium had been removed, so that the decrease in radioactivity could be used as an index of the amount of all kinds of impurity remaining in the ether layer. Experience has taught both the production and the laboratory chemist to view with suspicion a process which claims to separate one element from all others in the periodic system with a simple set of manipulations such as an extraction. Furthermore, there is the familiar example of iodide ion which anyone would expect to be oxidized to iodine and then be transferred almost quantitatively to the ether layer from which it would not wash out. It seemed reasonable that other elements or ions would be found which would fail to wash out of the ether layer. Since the objective was the removal of the neutron absorbers whether their danger coefficients were especially high ...
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Precipitation of Sodium Diuranate from Pitchblende Liquors

Precipitation of Sodium Diuranate from Pitchblende Liquors

Date: February 4, 1947
Creator: Brimm, E. O., Dr.
Description: In the treatment of carnotite concentrates, sodium diuranate was prepared by acidifying tricarbonate liquors to eliminate carbon dioxide, and then precipitating the sodium salt by the addition of caustic. Direct precipitation of uranium by the addition of caustic to tricarbonate liquors was used when pitchblende ores were processed, because this procedure was more effective in giving a product with a low molybdenum content. Tests of this method in the laboratory and Pilot Plant indicated that low uranium losses (0.2 to 0.3%) would be encountered with typical liquors if 1.7 to 2.0 lbs of caustic were added for every pound of uranosic oxide in solution. Since losses as high as 3% were incurred in plant operations, further work was undertaken, in an effort to reduce the uranium concentration in the waste liquors.
Contributing Partner: UNT Libraries Government Documents Department
The Precipitation of Uranium Peroxide in the Presence of Fluorides

The Precipitation of Uranium Peroxide in the Presence of Fluorides

Date: January 1, 1941
Creator: King, Edward J.
Description: The large-scale recovery of uranium from materials which also contained great quantities of fluorides did not give a product which had a low enough fluoride content to be treated satisfactorily by the other extraction process. The objective of the investigations carried out in this laboratory was a method of reducing the amount of fluoride which accompanied the uranium. The material from which the uranium was recovered in the industrial process was a slag containing (in addition to uranium) magnesium fluoride, calcium and dolomitic lines, crucible dross, and other waste products from the reaction of magnesium metal and uranium hexafluoride. Most of the fluoride was removed from this mixture by heating the roasted and ground slag with sulfuric acid. The residue was mixed with water and much of the caclium sulfate and fluoride, magnesium fluoride, and hydrated ferric oxide and alumina was precipitated by reducing the acidity. After filtering off the precipitate, ammonium sulfate was added to the solution and uranium peroxide (UO{sub 4} {center_dot} 2H{sub 2}O) was precipitated by addition of hydrogen peroxide. The pH of the solution was maintained between 3.0 and 3.5 during the precipitation by addition of sodium hydroxide. The uranium peroxide, even after washing, contained between ...
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Preparation and use of Ammonium Diuranate in the Ether Extraction Process

Preparation and use of Ammonium Diuranate in the Ether Extraction Process

Date: February 4, 1947
Creator: Brimm, E. O., Dr. & Mohr, P.
Description: In the ether extraction process, as originally developed, purified uranium dioxide was obtained by evaporation and calcination of the uranyl nitrate solution, followed by calcination of the resultant UO{sub 3}. It was suggested that an alternate procedure might be developed, involving the precipitation of uranium from the nitrate solution as ammonium diuranate. This material could then be calcined to uranosic acid, or reduced directly to the dioxide. It had already been established that ammonium diuranate could be precipitated completely from uranyl nitrate solutions. Experiments were carried out to determine whether a basic nitrate, analogous to a known sulfate salt, would be formed in the process. Both direct reduction of the diuranate to UO{sub 2} and calcination to uranosic acid were investigated to determine the physical characteristics and residual nitrogen of the resultant brown oxide.
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The Preparation of Uranium

The Preparation of Uranium

Date: August 26, 1948
Creator: Rodden, Clement J.
Description: The method used for the preparation of uranium metal in a fused state was reduction of uranium chloride with calcium in a refractory-lined bomb. The reaction was started by externally heating the bomb with a gas flame. The metal was obtained in a solid chunk which was covered with a layer of fused calcium chloride. The metal obtained by this process had a density of 17.6 which on remelting in a vacuum induction furnace rose to 18.8. The melting temperature of the metal was estimated to be no greater than 1400 C. The metal was malleable, and had a silvery surface when freshly cut which rapidly tarnished, becoming black in the course of a few days.
Contributing Partner: UNT Libraries Government Documents Department
Production of Uranium Metal

Production of Uranium Metal

Date: February 17, 1943
Creator: Nagy, R.
Description: Experiments were carried out for the purpose of increasing production, efficiency, and purity of uranium metal. The electrolytic method as described by Driggs and Lilliendahl for the preparation of uranium metal was followed with but little deviation. The yield of metal at the very best was only 50%. The metal powder produced, at times, was very pyrophoric. Methods were found whereby the metal, at least in part, can be made from the oxides with an average yield of about 90%. The small amounts of sludge and slag accumulated in this modified process can readily be re-used in the electrolysis pot and, therefore, an overall yield of 96% can be obtained. Information accumulated from these experiments has been compiled in such a manner as to be readily available for factory use, for patent purposes and for future publication.
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The Production of Uranium Metal by Metal Hydrides Incorporated

The Production of Uranium Metal by Metal Hydrides Incorporated

Date: January 1, 1943
Creator: Alexander, P. P.
Description: Metal Hydrides Incorporated was a pioneer in the production of uranium metal on a commercial scale and supplied it to all the laboratories interested in the original research, before other methods for its production were developed. Metal Hydrides Inc. supplied the major part of the metal for the construction of the first experimental pile which, on December 2, 1942, demonstrated the feasibility of the self-sustaining chain reaction and the release of atomic energy.
Contributing Partner: UNT Libraries Government Documents Department
Master-Slave Manipulator

Master-Slave Manipulator

Date: March 7, 1949
Creator: Goertz, R.C.
Description: A device for manipulating a pair of tongs behind a shielding barrier has been built and tested. It is called a Master-Slave Manipulator because the slave tongs move in exact correspondence with a master handle. The "slave hands" follow the master hands in complete synchronism. This is the first completely master-slave manipulator known to exist and has proved that this type of manipulation is very successful when the unit is prooperly engineered and built.
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Cloud Chamber: Heat Shielding, Magnet Shielding

Cloud Chamber: Heat Shielding, Magnet Shielding

Date: 1946
Creator: Hering, D.
Description: Technical drawing of a cloud chamber and ionization chamber for use in nuclear reactors.
Contributing Partner: UNT Libraries Government Documents Department
Cloud Chamber: Camera Lights Assembly

Cloud Chamber: Camera Lights Assembly

Date: 1946
Creator: Hering, D.
Description: Technical drawing of cloud chamber and ionization chamber for use in a nuclear reactor.
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Model 411 Scaler

Model 411 Scaler

Date: 1947
Creator: Sewell, C.
Description: Technical drawing of counters and circuits for use in nuclear reactors.
Contributing Partner: UNT Libraries Government Documents Department
Wilson 4" Pump Valve

Wilson 4" Pump Valve

Date: 1947
Creator: U.S. Atomic Energy Commission
Description: Declassified Manhattan Project technical drawings of pumping machinery in nuclear reactors.
Contributing Partner: UNT Libraries Government Documents Department
[Technical Drawings: Spiral Carrier]

[Technical Drawings: Spiral Carrier]

Date: 1947
Creator: U.S. Atomic Energy Commission
Description: Technical drawings of screw conveyors for use in nuclear reactors.
Contributing Partner: UNT Libraries Government Documents Department
Lower Drive Assembly

Lower Drive Assembly

Date: 1947
Creator: U.S. Atomic Energy Commission
Description: Technical drawings for construction of the lower drive assembly for a nuclear reactor.
Contributing Partner: UNT Libraries Government Documents Department
[Technical Drawings: Building 706-D]

[Technical Drawings: Building 706-D]

Date: 1947
Creator: Monsanto Chemical Company
Description: Technical drawings of pipettes for use in nuclear reactors.
Contributing Partner: UNT Libraries Government Documents Department
Alpha Chamber

Alpha Chamber

Date: 1947
Creator: United States. Office of Scientific Research and Development. Metallurgical Laboratory.
Description: Technical drawings detailing alpha rays in a nuclear reactor cloud chamber.
Contributing Partner: UNT Libraries Government Documents Department
Alpha Chamber Modified

Alpha Chamber Modified

Date: 1947
Creator: United States. Office of Scientific Research and Development. Metallurgical Laboratory.
Description: Technical drawings for alpha rays in a nuclear reactor cloud chamber.
Contributing Partner: UNT Libraries Government Documents Department