A MACRO GRAIN SIZE TECHNIQUE FOR URANIUM (open access)

A MACRO GRAIN SIZE TECHNIQUE FOR URANIUM

None
Date: February 1, 1956
Creator: Gardner, H.R.
Object Type: Report
System: The UNT Digital Library
GRAIN REFINEMENT PRODUCED BY AN ALPHA PHASE ANNEAL OF BETA PHASE HEAT TREATED AND WATER QUENCHED URANIUM (open access)

GRAIN REFINEMENT PRODUCED BY AN ALPHA PHASE ANNEAL OF BETA PHASE HEAT TREATED AND WATER QUENCHED URANIUM

During an experiment involving alpha phase annealing (at 610 to 655 deg C for 5 and 10 min) of beta-quenched uranium, it was determined that the relatively coarse, irregular shaped grains (0.08 to 0.150 mm in diameter) in the beta-quenched structure, were replaced by fine equiaxed grains (0.04 to 0.09 mm in diameter). (auth)
Date: January 1, 1955
Creator: Gardner, H.R.
Object Type: Report
System: The UNT Digital Library
TRANSIENT HEATING OF UC FUEL ELEMENTS IN THE KEWB FACILITY (open access)

TRANSIENT HEATING OF UC FUEL ELEMENTS IN THE KEWB FACILITY

The feasibility of using the KEWB reactor as a pulsed neutron radiation source for use in studies of fuel element transient heating was studied. UC fuel rod samples were heated in the reactor. It was found that flux distribution in fuel samples could be mapped and thermal conductivity measurements for UC could be made by using fast response thermocouples distributed radially in the sample. (J. R.D.)
Date: September 1, 1959
Creator: Gardner, E.L. & Barnes, S.G.
Object Type: Report
System: The UNT Digital Library
RECYCLE OF UO$sub 2$F$sub 2$ IN THE FLUOROX PROCESS: REACTION OF UO$sub 2$F$sub 2$ WITH HYDROGEN (open access)

RECYCLE OF UO$sub 2$F$sub 2$ IN THE FLUOROX PROCESS: REACTION OF UO$sub 2$F$sub 2$ WITH HYDROGEN

The reaction of U0/sub 2/F/sub 2/ with hydrogen at 700 to 850 deg C was briefly investigated since it could constitute a major step in the recycle of U0/ sub 2/F/sub 2/ in the Fluorox process. The reaction in this temperature range proceeds according to the equation U0/sub 2/F/sub 2/ + H/sub 2/ yields U0/sub 2/ + 2 HF. Rates of the chemical reaction were not obtsined, since, with the thermogravimetric technique used, the rate-controlling process was bed diffusion. However, there is no doubt that the rate of chemical reaction is sufficiently high for the desired application. No significant amount of UF/sub 4/ was formed by the back-reaction, U0/sub 2/ + 4 HF yields UF/sub 4/ + 2 H/sub 2/0. (auth)
Date: July 1, 1959
Creator: Ferris, L.M. & Gardner, R.P.
Object Type: Report
System: The UNT Digital Library
The Gravimetric Determination of Tungsten in Uranium-Tungsten Alloys (open access)

The Gravimetric Determination of Tungsten in Uranium-Tungsten Alloys

Tungsten in uranium--tungsten alloys is determined by precipitating the tungsten from a cold sulfuric acid solution using alpha -benzoinoxime and cinchonine as the precipitating agents. The precipitate is dgnited at 800 deg C and weighed as WO/sub 3/. Results of 94 determinations on known samples containing 20 to 40 milligrams of tungsten in the presence of 1 to 8 grams of uranium showed an average recovery of 100.1% with a standard deviation of 0.7%. (auth)
Date: September 1, 1958
Creator: Carpenter, R. L.; Gardner, R. D.; Ashley, W. H. & Henicksman, A. L.
Object Type: Report
System: The UNT Digital Library
The Determination of Chlorine in Polyurethane Plastic (open access)

The Determination of Chlorine in Polyurethane Plastic

Chlorine may be determined in polyurethane by gravimetric or spectrophotometric techniques. The sample is burned in a special combustion tube with two oxygen inlets, the products of combustion are absorbed in a solution containing sodium hydroxide and hydrogen peroxide, and the chlorine is measured either gravimetrically as silver chloride or spectrophotometrically using mercuric thiocyanate and ferric perchlorate. Eighteen determinations of cblorine in known solutions of sodium chloroacetate or perchloric acid gave an average recovery of 98.3% with a standard deviation of 2.8%. (auth)
Date: October 1, 1959
Creator: Henicksman, A. L.; VanKooten, E. H.; Gardner, R. D. & Ashley, W. H.
Object Type: Report
System: The UNT Digital Library
MECHANICAL PROPERTY AND FORMABILITY STUDIES ON UNALLOYED PLUTONIUM (open access)

MECHANICAL PROPERTY AND FORMABILITY STUDIES ON UNALLOYED PLUTONIUM

The effect of temperature and testing speed on the tension and compression properties of unalloyed plutouium was studied in the alpha , beta , gamma , and delta phases. Compressive formability data were obtained for a load of 100,000 lbs in the aforementioned phases. In addition, preliminary creep, tension impact, and torsion data for alpha -phase plutonium are reported. Extrusion constants and pressures for the beta , gamma , and delta phases were obtained. The roomtemperature tension and compression properties of the beta - and #gg-extruded plutonium were determined. Metallo graphic studies were made to determine the effect of tension, compression, and extrusion, in the indicated phases, on the microstructure of as-cast plutonium. (auth)
Date: December 1, 1959
Creator: Gardner, H.R. & Mann, I.B.
Object Type: Report
System: The UNT Digital Library
The Chickasha Star (Chickasha, Okla.), Vol. 50, No. 31, Ed. 1 Thursday, May 1, 1952 (open access)

The Chickasha Star (Chickasha, Okla.), Vol. 50, No. 31, Ed. 1 Thursday, May 1, 1952

Weekly newspaper from Chickasha, Oklahoma that includes local, state and national news along with advertising.
Date: May 1, 1952
Creator: Kayser, J. W.
Object Type: Newspaper
System: The Gateway to Oklahoma History
KEWB Program Quarterly Progress Report: July-September 1956 (open access)

KEWB Program Quarterly Progress Report: July-September 1956

From abstract: The response of the reactor to forced oscillations has been investigated with the pile oscillator technique and the data are presently being analyzed.
Date: March 1, 1957
Creator: North American Aviation. Atomics International Division. Kinetic Experiments on Water Boilers Program.
Object Type: Report
System: The UNT Digital Library
The Response of a Water Boiler Reactor to Very Fast Power Transients and Linearly Increasing Reactivity Inputs. Water Boiler Excursions With an Initially Filled Core (open access)

The Response of a Water Boiler Reactor to Very Fast Power Transients and Linearly Increasing Reactivity Inputs. Water Boiler Excursions With an Initially Filled Core

A report is made on the Kinetic Experiment on Water Beller Program. The purpose of this program is to examine the dynamic behavior of homogeneous research reactors to obtain the information necessary for the evaluation of the nuclear safety of such reactors. Step inputs of reactivity were systematically increased and the first test core, a spherical core designed for stable power operation at 50 kw, was examined under conditions of 4% reactivity release This is the maximum normally installed in such reactors A 4% reactivity release places the reactor on a 2 millisecond stable period and leads to a peak power of 530 Mw. This represents the fastest intentional power excursion of any thermal reactor. The reactivity released is more than twice that which any other has withstood without damage. The maximum pressure in the system for this transient was a sharp pressure peak of 370 psia. This pressure is well below that required to cause yield of a typical water boller core. (A.C.)
Date: September 1, 1958
Creator: Stitt, R. K.; Gardner, E. L.; Roecker, J. H.; Wimmer, R. E. & Hetrick, D. L.
Object Type: Report
System: The UNT Digital Library
Grain Refinement of Cast Uranium by Heat Treatment (open access)

Grain Refinement of Cast Uranium by Heat Treatment

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)
Date: July 1, 1957
Creator: Powell, G. W.; Klein, J. L. & Krashes, D.
Object Type: Report
System: The UNT Digital Library
Electronic Specific Heat of Sodium Tungsten Bronze (open access)

Electronic Specific Heat of Sodium Tungsten Bronze

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 …
Date: March 1, 1957
Creator: Vest, R. W.; Griffel, M. & Smith, J. F.
Object Type: Report
System: The UNT Digital Library
Activation Analysis Nuclear Chemical Research Radiochemical Separations. Progress Report No. 8 for November 1958-October 1959 (open access)

Activation Analysis Nuclear Chemical Research Radiochemical Separations. Progress Report No. 8 for November 1958-October 1959

Activities at the Michigan Reactor and pneumatic tube system are outlined. Various modifications including installation and operation of a "bunny" rabbit pneumatic tube system for transferring samples from laboratory to counter are described. Prelimirary investigation for design of a neutron generator for activation work is described. Modifications to the 100-channel pulse-height analyzer including addition of auxillary circuits and additioral detectors are sumnnarized. In nuclear chemistry a cyclotron bombardment to produce long-lived vanadium tracer for yield determinations in activation analysis is described. Summaries of project work which have been published on absolute (d, alpha) reaction cross sections and excitation functions, use of computers in nuclear data analysis, and research on Ir/sup 196/ are presented. Study of the gamma spectra of 33-second Kr/sup 90/, 41-second Xe/sup 139/, and some longer-lived fission product rare gases is reported and a summary of preliminary results is given. Detection of a long-lived isomer of Ag/sup 108/ in old Ag/sup 110m/ samples is reported and new values for the branching ratios of 2.4minute Ag/sup 108/ are given. Activities of the Subcommittee on Radiochemistry are summarized. Development of a radiochemical procedure by the use of amalgam exchange is reported and exchange of the elements Cd, Tl, Zn, Pb, …
Date: November 1, 1959
Creator: Maddock, R. S. & Meinke, W. W.
Object Type: Report
System: The UNT Digital Library
Nuclear Chemical Research, Radiochemical Separations and Activation Analysis: Progress Report 7, November 1957 - October 1958 (open access)

Nuclear Chemical Research, Radiochemical Separations and Activation Analysis: Progress Report 7, November 1957 - October 1958

Progress report discussing projects and work completed by the University of Michigan Department of Chemistry 1957-1958.
Date: November 1, 1958
Creator: Meinke, W. W.
Object Type: Report
System: The UNT Digital Library
IGNITION BEHAVIOR AND KINETICS OF OXIDATION OF THE REACTOR METALS, URANIUM, ZIRCONIUM, PLUTONIUM, AND THORIUM, AND BINARY ALLOYS OF EACH. A Status Report (open access)

IGNITION BEHAVIOR AND KINETICS OF OXIDATION OF THE REACTOR METALS, URANIUM, ZIRCONIUM, PLUTONIUM, AND THORIUM, AND BINARY ALLOYS OF EACH. A Status Report

>The importance of prevention of fires and explosions involving uranium, zircomum, plutonium, and thorium, which are of particular interest to the nuclear energy program, made imperative the study of their ignition behavior and oxidation kinetics. Methods of measurements of ignition characteristics of uranium and zirconium were developed and used to determine the effects of variables, such as surface preparation, metallurgical history, specific area (sample size), additives to the metal, and oxygen content and presence of moisture in the oxidizing gas. The study of ignition characteristics was supported by study of the effects of similar variables on the kinetics of oxidation of uranium and zirconium and binary alloys of each. The oxidation of uranium always proceeded in two linear stages over the temperature range of 125 to 295 deg C at pressures of 20, 50, 200, and 800 mm of oxygen. The temperature dependences of both stages indicate an activation energy dependent on pressure. The presence of ten additive elements in uranium metal caused only very small effects on the oxidation. The oxidation of zirconium was independent of pressure and proceeded according to a cubic rate law over the temperature range from 400 to 900 deg C, with an activation energy …
Date: April 1, 1959
Creator: Schnizlein, J. G.; Pizzolato, P. J.; Porte, H. A.; Bingle, J. D.; Fischer, D. F.; Mishler, L. W. et al.
Object Type: Report
System: The UNT Digital Library
The Kinetic Behavior of Water Boiler Type Reactors (open access)

The Kinetic Behavior of Water Boiler Type Reactors

None
Date: April 1, 1956
Creator: Remley, M. E.; Flora, J. W.; Hetrick, D. L. & Inglis, L. P.
Object Type: Report
System: The UNT Digital Library
Tabulated Neutron Cross Sections. Part 1. 0.001-14.5 Mev. Volume 2. $sub 23$v-$sub 20$Sn (open access)

Tabulated Neutron Cross Sections. Part 1. 0.001-14.5 Mev. Volume 2. $sub 23$v-$sub 20$Sn

Tables of neutron total, elastic, inelastic, scattering, and absorption cross sections are presented for the elements V through Sn at 0.001 to 14.5 Mev. (C.J.G.)
Date: October 1, 1959
Creator: Howerton, Robert J.
Object Type: Report
System: The UNT Digital Library
TABULATED NEUTRON CROSS SECTIONS, PART 1. 0.001-14.5 MEV. VOLUME 1. $sub 1$H-$sub 22$Ti (open access)

TABULATED NEUTRON CROSS SECTIONS, PART 1. 0.001-14.5 MEV. VOLUME 1. $sub 1$H-$sub 22$Ti

Tables of neutron total, elastic, inelastic, scattering, and absorption cross sections are presented for the elements hydrogen through titanium at 0.001 to 14.5 Mev. (C.J.G.)
Date: October 1, 1959
Creator: Howerton, R. J.
Object Type: Report
System: The UNT Digital Library
The Meson Mass Ratio and Energy Balance in Pi-Mu Decay (open access)

The Meson Mass Ratio and Energy Balance in Pi-Mu Decay

None
Date: March 1, 1954
Creator: Birnbaum, W.
Object Type: Thesis or Dissertation
System: The UNT Digital Library
Health Protection in Beryllium Facilities Summary of Ten Years of Experience (open access)

Health Protection in Beryllium Facilities Summary of Ten Years of Experience

From Introduction: "The purpose of this report is to summarize the information gathered during the design and operation of these facilities so that it may be used in providing for the safe handling of beryllium materials."
Date: May 1, 1958
Creator: Breslin, A. J. & Harris, W. B.
Object Type: Report
System: The UNT Digital Library
Polk County Enterprise (Livingston, Tex.), Vol. 72, No. 28, Ed. 1 Thursday, April 1, 1954 (open access)

Polk County Enterprise (Livingston, Tex.), Vol. 72, No. 28, Ed. 1 Thursday, April 1, 1954

Weekly newspaper from Livingston, Texas that includes local, state and national news along with advertising.
Date: April 1, 1954
Creator: Lewis, John W.
Object Type: Newspaper
System: The Portal to Texas History
The Crosbyton Review. (Crosbyton, Tex.), Vol. 44, No. 18, Ed. 1 Thursday, May 1, 1952 (open access)

The Crosbyton Review. (Crosbyton, Tex.), Vol. 44, No. 18, Ed. 1 Thursday, May 1, 1952

Weekly newspaper from Crosbyton, Texas that includes local, state and national news along with advertising.
Date: May 1, 1952
Creator: Curry, W. H.
Object Type: Newspaper
System: The Portal to Texas History
The Daily News-Telegram (Sulphur Springs, Tex.), Vol. 53, No. 260, Ed. 1 Thursday, November 1, 1951 (open access)

The Daily News-Telegram (Sulphur Springs, Tex.), Vol. 53, No. 260, Ed. 1 Thursday, November 1, 1951

Daily newspaper from Sulphur Springs, Texas that includes local, state, and national news along with advertising.
Date: November 1, 1951
Creator: Frailey, F. W.
Object Type: Newspaper
System: The Portal to Texas History
Polk County Enterprise (Livingston, Tex.), Vol. 72, No. 41, Ed. 1 Thursday, July 1, 1954 (open access)

Polk County Enterprise (Livingston, Tex.), Vol. 72, No. 41, Ed. 1 Thursday, July 1, 1954

Weekly newspaper from Livingston, Texas that includes local, state and national news along with advertising.
Date: July 1, 1954
Creator: Lewis, John W.
Object Type: Newspaper
System: The Portal to Texas History