Development of Forging Techniques for Uranium (open access)

Development of Forging Techniques for Uranium

Uranium has been successfully forged using a Lobdell-Nazel forging hammer and a forging temperature range of 500 to 650 degrees centigrade. Using standard forging techniques, the metal readily flowed at the temperature chosen. A noticeable increase in tensile strength, yield strength and percent elongation was obtained in forged metal as compared with cast metal. To obtain complete recrystallization and uniform grain size, a minimum of approximately 75 percent reduction in cross section by forging followed by an anneal within the range of 500 to 600 degrees C is required.
Date: November 1, 1950
Creator: Anderson, R. E.; Taub, J. M. & Doll, D. T.
System: The UNT Digital Library
Fast Neutron Cross Sections: Corrections to LA-1714 and a Correlation of 3 Mev Values (open access)

Fast Neutron Cross Sections: Corrections to LA-1714 and a Correlation of 3 Mev Values

Recent measurements on the long counter efficiency in which comparisons were made with the (n, p) scattering cross section, additional variations in efficiency were found which varied slowly with neutron energy but were still correlated with the total neutron cross section of carbon. Because of these variations in efficiency there are errors in the fission cross sections reported in LA-1714. Corrections to these data have been given here.
Date: March 1, 1957
Creator: Henkel, Richard L.
System: The UNT Digital Library
A Determination of the Coefficient of Thermal Expansion of Alpha Plutonium (open access)

A Determination of the Coefficient of Thermal Expansion of Alpha Plutonium

The coefficient of linear expansion of alpha plutonium has been determined for the range -180 to +100 degree C by the silicon-tube and dial-indicator method. The value of the expansion coefficient is reported as [formula]. Included are a detailed description of the apparatus and a discussion of the method.
Date: March 1, 1952
Creator: Elliott, R. O. & Tate, R. E.
System: The UNT Digital Library
The Nickel-Plutonium System (open access)

The Nickel-Plutonium System

A tentative nickel-plutonium constitutional diagram was based on data obtained by thermal analysis, metallography, and x-ray-diffraction techniques. The systema is a complex one with the following important features. Nickel is soluble in epsilon plutonium, extending the epsilon field to 4.3 at.% nickel at 465 deg C. Nickel and plutonium form six intermetallic compounds, PuNi, EnNi/sub 2/, PuNi/sub 3/, PuNi/sub 4/, PuNi/sub 5/, and PuNi/sub 9/. The compound PuNi/ sub 5/ forms congruently from the melt at approximately l300 deg C, whereas the other compounds form peritectoidally. The extended epsilon field terminates in a eutectoid reaction at 415 deg C and l.5 at.% nickel. Epsilon plutonium and the compound PuNi form a eutectic system at 465 deg C with a eutectic composition of l2.5 at,% nickel. Nickel and the compound PuNi/sub 9/ form a eutectic system at l2l0 deg C with a eutectic composition of 92 at.% nickel. Plutonium forms a limited solid solution with nickel.
Date: March 1, 1951
Creator: Wensch, Glen William, 1917-; Whyte, D D.; Cramer, E M.; Ellinger, F H.; Schonfeld, F W. & Struebing, V O.
System: The UNT Digital Library
The Determination of Oxygen in Plutonium by the Capillary Trap Method (open access)

The Determination of Oxygen in Plutonium by the Capillary Trap Method

A new method for the determination of O/sub 2/ in metals is described. The sample is dropped into molten Pt in a graphite crucible. The oxide in the sample reacts with C to form CO, which is swept out by a stream of argon at atmospheric pressure. The CO is oxidized to CO/sub 2/, which is condensed in a capillary trap and measured with a capillary manometer. The apparatus is sensitive to 0.3 mu g of O/sub 2/, and routine 50-mg Pu samples give a standard deviation of 7 ppm or 0.35 mu g. Pu samples with added O/sub 2/ gave a standard deviation of 1.5 mu g or 2% of the total oxygen, with no significant bias. The apparatus is simple and rugged permitting replacement of parts without glassblowing. The speed is superior to vacuum fusion methods, most samples requiring only twelve minutes for analysis.
Date: February 1, 1953
Creator: Smiley, William G. (William Gooding), 1915-
System: The UNT Digital Library
Exploratory Studies of Hydrazine Formation by Radioactive Ionization (open access)

Exploratory Studies of Hydrazine Formation by Radioactive Ionization

The production yields of hydrazine by various ionization methods are compared. The maximum value of M/N (number of molecules reacting per ion pairs) for electric discharge was 0.25 and for beta particles on liquid ammonia, M/N = 0.31. A 1-Mev reactor could produce 1.6 kg of hydrazine per hour if M/N = 0.04 as determined by alpha particles on liquid ammonia. About 300 ev of energy were needed to form a hydrazine molecule. (C.J.G.)
Date: June 1, 1951
Creator: Busey, Harold M.
System: The UNT Digital Library
Remote Control Equipment for Plutonium Metal Production (open access)

Remote Control Equipment for Plutonium Metal Production

Design and construction of remote control equipment for plutonium metal production are described. Criteria for the design of the equipment included the following: rubber gloves were to be completely eliminated; all mechanisms were to be built as integral units to facilitate replacement through use of the plastic- bag technique; no accessory equipment such as switches, valves, piping, or cylinders were to be inside the contaminated enclosure unless required to handle the plutonium; and all units were to be tested in mockups before final design. The chemical process, general layout, and operating function are outlined. Descriptions are given of all mechanical units, electrical systems, hydroxide slurry systems, ventilation systems, and chemical tanks and manifolds. (W.L.H.)
Date: October 1, 1951
Creator: Hazen, Wayne C.
System: The UNT Digital Library
Some Observations on the Reactivity of Plutonium Dioxide (open access)

Some Observations on the Reactivity of Plutonium Dioxide

The index of refraction of PuO2 made by thermal decomposition of PU(C2O2, 6H2O gradually increases from a value < 1.9 to 2.40 as the decomposition temperature is increased from 150 degree to l000 degree C. This change in refractive index parallels a gradual change in the x-ray diffraction pattern from weak, diffuse lines for PuO2 ignited at 150° to sharp, well resolved lines for PuO2 ignited at 1000°C. Similar results are observed for PuO2 made by thermal decomposition of Pu2(C2O4)3*11H2O. The refractive index of PuO2 made from Pu metal at 170°C is 2.40 and is not affected by further ignition at higher temperatures, although crystal growth does occur. The rate of solution of PuO2 in an HCl-KI solution is greatest for samples prepared at low temperatures and decreases markedly for oxides ignited at higher temperatures. These observations hive been interpreted to mean that ignition at higher temperatures causes a gradual perfection of the originally highly distorted and impurity-containing PuO2 lattice obtained by low temperature decomposition of the oxalates and promotes the slow growth of crystallites. Both factors decrease the reactivity of the PuO2.
Date: September 1, 1954
Creator: Bjorklund, C.W. & Staritzky, Eugene
System: The UNT Digital Library
Forming of Uranium in the Gamma Phase Temperature Range (open access)

Forming of Uranium in the Gamma Phase Temperature Range

It has been found relatively easy to form uranium in the gamma phase temperature range by hot pressing, forging, or extrusion. The metal is quite plastic and flows readily to form a shape. Several temperatures from 800 degree C to 1000 degree C were investigated. No forming difficulties were experienced with the metal at the several temperatures concerned. The major difficulty in gamma phase hot pressing or extruding was associated with the tools. Metals or ceramics were not successful as tools for one or more reasons concerned with: lack of hot strength, reactions with the uranium, failure in thermal shock, and tendency to spall. Graphite was found to be the best material available, but it is not entirely satisfactory because of low strength. Uranium formed in the gamma phase possesses some refinement of grain structure as compared with as-cast metal; however, the grain size is quite large. No physical properties of the gamma phase formed metal were determined.
Date: May 1, 1951
Creator: Levinson, L. S.; Cribble, W. C.; Taub, J. M. & Doll, D. T.
System: The UNT Digital Library
Fusion Welding of Uranium (open access)

Fusion Welding of Uranium

A technique for the fusion welding of uranium has been under development and several methods of fusion welding have been investigated. The inert gas, shield arc method has proven to be the most satisfactory of the processes thus far examined. Uranium properly weld by this method was free from porosity, cracks, and oxide inclusions. Certain precautions and some special techniques were required to make good welds.
Date: August 1, 1952
Creator: Nelson, V. G.; Taub, J. N. & Dell, D. T.
System: The UNT Digital Library
Effect of Annealing Media on the Mechanical Properties of Uranium (open access)

Effect of Annealing Media on the Mechanical Properties of Uranium

The annealing or heat treatment of uranium in any medium other than a good vacuum or purified helium atmosphere, will lower the room temperature properties of ultimate strength, hardness and elongation. In general, the elongation of vacuum annealed uranium exceeds considerably the elongation of air or salt annealed uranium. Any annealing medium which permits contact of the uranium metal with atmospheric gases tends to produce low elongation and ductility and a lowering of the ultimate strength. The above is true for uranium in any solid form, whether it is rolled sheet, cast bars or plates, rolled rod, or extruded shapes. Annealing in the molten salt bath (65% potassium carbonate and 35% lithium carbonate), which is used by Los Alamos and other laboratories concerned with the fabrication of uranium, produces the lowest elongation or ductility and ultimate strength when compared to similar properties of metal annealed in the other media examined. Mass spectrometer analyses of the dissolved gases present in high ductility and low ductility uranium indicate that dissolved hydrogen is probably the chief cause of low physical properties.
Date: August 1, 1953
Creator: Hanks, G. S.; Taub , J. M. & Doll , D. T.
System: The UNT Digital Library
Collected Reports on Fission Cross Sections of U237 in Thermal Neutron, Intermediate Neutron, and Degraded Fission Neutron Spectra (open access)

Collected Reports on Fission Cross Sections of U237 in Thermal Neutron, Intermediate Neutron, and Degraded Fission Neutron Spectra

Part 1. The neutron fission cross section of U237 has been measured in a thermal neutron spectrum and in a somewhat degraded fission spectrum. The fission cross section for thermal neutrons is found to be <2 barns; the ratio of the fission cross section of U237 to that of U235 in the degraded fission spectrum is found to be 0.476 +- 15% which corresponds to [formula] in this spectrum equal to 0.66 +- 0.10 barns. Part 2. The average neutron fission cross section of U237 has been measured in a neutron energy range extending from approximately 100 ev to fission spectrum. the average fission cross section in this spectrum is found to be 0.70 +- 0.07 barns. Part 3. The low thermal fission cross section for U237 (<2 barns) indicated that the excitation function for fission probably shows an effective threshold. If the excitation function is like all other heavy element (Z > 90) neutron fission excitation functions, it will exhibit a region of approximate constancy starting at a neutron energy of 0.5 to 1 Mev above its effective threshold and extending to a neutron energy in the neighborhood of 5.5 Mev. A hypothetical excitation function for neutron fission of …
Date: January 1, 1955
Creator: Cowan, G. A. (George A.), 1920-2012
System: The UNT Digital Library
The Preparation of the Hydrides of Magnesium and Beryllium (open access)

The Preparation of the Hydrides of Magnesium and Beryllium

This technical report summarizes the work which has been done to date on the preparation of magnesium hydride and the attempted preparation of beryllium hydride. Although pure beryllium hydride has not yet been made, the work is continuing, and this report indicates which phases are thought to be worth further work.
Date: April 1, 1954
Creator: Holley, Charles E., Jr.
System: The UNT Digital Library
Predicted Structure and Density of Beryllium Hydride (open access)

Predicted Structure and Density of Beryllium Hydride

Various properties of BeH/sub 2/ are predicted, based on the properties of neighboring hydrides. Included are predictions of the stability of the Be-H bond, the stability of an ionic lattice for BeH/sub 2/, polymeric structure, and density.
Date: December 1, 1953
Creator: Lemons, Jim F.; Lewis, W. B.; Fowler, R. D.; Staritzky, Eugene & Holley, Charles E., Jr.
System: The UNT Digital Library
Fabrication of Plutonium Ingots From Plutonium Turnings (open access)

Fabrication of Plutonium Ingots From Plutonium Turnings

Kilogram quantities of delta-stabilized and pure plutonium turnings can be cast directly into ingots of normal quality with high yields. This report describes the equipment and process used.
Date: December 1, 1956
Creator: Johnson, Karl W. R.
System: The UNT Digital Library
Some Observations on the Reactivity of Plutonium Dioxide (open access)

Some Observations on the Reactivity of Plutonium Dioxide

The index of refraction of PuO2 made by thermal decomposition of PU(C2O2, 6H2O gradually increases from a value < 1.9 to 2.40 as the decomposition temperature is increased from 150 degree to l000 degree C. This change in refractive index parallels a gradual change in the x-ray diffraction pattern from weak, diffuse lines for PuO2 ignited at 150° to sharp, well resolved lines for PuO2 ignited at 1000°C. Similar results are observed for PuO2 made by thermal decomposition of Pu2(C2O4)3*11H2O. The refractive index of PuO2 made from Pu metal at 170°C is 2.40 and is not affected by further ignition at higher temperatures, although crystal growth does occur. The rate of solution of PuO2 in an HCl-KI solution is greatest for samples prepared at low temperatures and decreases markedly for oxides ignited at higher temperatures. These observations hive been interpreted to mean that ignition at higher temperatures causes a gradual perfection of the originally highly distorted and impurity-containing PuO2 lattice obtained by low temperature decomposition of the oxalates and promotes the slow growth of crystallites. Both factors decrease the reactivity of the PuO2.
Date: November 1, 1954
Creator: Bjorklund, C.W. & Staritzky, Eugene
System: The UNT Digital Library