Partner
Oklahoma Historical Society
16,237
UNT Libraries Special Collections
6,564
UNT Libraries Government Documents Department
2,364
Rosenberg Library
1,904
UNT College of Visual Arts + Design
863
Hardin-Simmons University Library
837
UNT Libraries
589
Oklahoma Conservation Historical Society
443
Abilene Public Library
366
Hopkins County Genealogical Society
360
231 More
Collection
Texas Digital Newspaper Program
8,797
Oklahoma Digital Newspaper Program
8,219
Oklahoma Publishing Company Photography Collection
7,729
Tocker Foundation Grant
4,160
KXAS-NBC 5 News Collection
3,094
Harris and Eliza Kempner
1,906
University Photography Collection
1,557
Abilene Library Consortium
1,517
Office of Scientific & Technical Information Technical Reports
1,229
The Oklahoma City Times
1,062
374 More
Degree Department
Degree Discipline
Degree Level
Country
States
Year
Month
THE CRYSTAL STRUCTURE OF LiCuCl$sub 3$ /center dot/ 2H$sub 2$O
None
Date:
August 1, 1960
Creator:
Vossos, P. H.; Fitzwater, D. R. & Rundle, R. E.
Object Type:
Report
System:
The UNT Digital Library
Ionium, Uranium-232, and Thorium-228 Properties, Applications and Availability
Charts are given which present information on the properties, sources, and uses of Th/sup 230/, Th/sup 228/, and U/sup 232/ They also compare these properties with competitive isotopes. (M.C.G.)
Date:
August 1, 1960
Creator:
Rohrmann, C.A.
Object Type:
Report
System:
The UNT Digital Library
The Salt Cycle Process
The Salt Cycle Process is a nuclear fuel processing approach designed for application in compact facilities located at the reactor sites. Irradiated UO/sub 2/ fuels would be processed through a brief sequence of steps and partially purified UO/sub 2/ or UO/sub 2/--PuO/sub 2/ powders recovered, suitable for refabrication into fuel elements. The major steps of the process are the dissolution of uranium oxides in molten NaCl--KCl eutectic by chlorination to form soluble uranyl chloride and the reduction of uranyl chloride to UO/sub 2/, which separates as a solid. The preferred method of reduction is the electrolytic method, which yields UO/sub 2/ as a conveniently handled, adherent deposit on the cathode. Means are described for separation of Pu from U and for co-deposition of the Uo. Also included are discussions of the probable nature of the U and Pu species present in the molten salt, side reactions in which uranyl chloride may participate, and the influence of certain variables on the properties of the UO/sub 2/ produced. (auth)
Date:
August 1, 1960
Creator:
Benedict, G.E.; Lyon, W.L.; Mudge, L.K.; Swanson, J.L. & Walling, M.T. Jr.
Object Type:
Report
System:
The UNT Digital Library
Modified Purification System Performance Test. Core I, Seed 2. Test Results (T-641124). Section 1
An investigation was conducted to establish an operating procedure for flushing water through a purification system demineralizer which was out of service for an extended period, and to determine the demineralizer serviceability. (J.R.D.)
Date:
September 14, 1960
Creator:
Duquesne Light Company
Object Type:
Report
System:
The UNT Digital Library
Radiation Hazards Encountered in Arc Melting Thorium
A project to provide information on the hazards associated wlth arc melting of Th is described. A general airsampling analysis was made to determine the separation, concentration, and distribution of Th daughter (decay) products throughout arc melting, machining, and forging processes found in a handling facility. The value of well coordinated health physics program is stressed in connection with potential health hazards and personnel protection. Building, equipment, and exhaust ventilation requirements for such a facility are discussed, along wlth special handling methods. (auth)
Date:
November 1, 1960
Creator:
Lowery, R. R.
Object Type:
Report
System:
The UNT Digital Library
TEST OF GERMAN UNDERGROUND PERSONNEL SHELTERS
The predicted behavior of German underground personnel shelters, equipment, and certain instrumentation was investigated. Data obtained will be used for evaluation and improvement of present design criteria. Nine reinforcedconcrete underground shelters, designed by German engineers, were tested at the 170-, 155-, 110-, 78-, 26-, 11.5-, and 7.2-psi overpressure ranges as determined from average blast-line instrumentation measurements. Reinforcing steel, doors, and ventilation equipment were received and incorporated in the shelters. Preshot and postshot precise location surveys were made to determine the total lateral and vertical motions of the structure as a result of the blast. Blast instrumentation used in the shelters and entranceways consisted of pressure gauges, earthpressure gauges, self-recording pressure gauges, and dynamic pressure gauges. Free-field measurements were recorded along the blast line using U. S. self-recording and electronic pressure gauges and German self- recording pressure gauges. Structural response was recorded by deflection and acceleration gauges, strain gauges, and scratch gauges. Radiation measurements were taken using U. S. gamma-radiation film dosimeters, gamma-radiation chemical dosimeters, neutron detectors, telemetering gamma dosimeters, and German gamma chemical dosimeters. Mice were used as biological specimens in environmental tests in seven of the nine structures tested. In addition to the environmental tests, a series of tests …
Date:
July 1, 1960
Creator:
Cohen, E. & Bottenhofer, A.
Object Type:
Report
System:
The UNT Digital Library
Reactor Materials Study. Research and Development of Metal Hydrides. Quarterly Report No. 7 for April 1, 1960 to June 30, 1960
High-temperature x-ray diffraction experiments provided confirming evidence regarding the origin of the metastable gamma phase and of the general features of the zirconiumhydrogen phase system. These experiments also showed that the reaction alpha + delta -- beta (the eutectoid reactlon on heating) proceeds at an extraordinarily slow rate, although the reverse reaction proceeds so rapidly that beta phase cannot be retained to room temperature by quenching. The sluggishness of the eutectoid reaction on heating undoubtedly resulted in erroneous interpretation of certain physical and mechanical properties determined of the mechanical properties of zirconium hydride containing various minor alloy additions is continuing. Although these data are still quite sketchy, alloy additions of 5 at.% Sc or 2.2 at.% Cu show the most promise at this time. (auth)
Date:
July 1, 1960
Creator:
Beck, R. L.
Object Type:
Report
System:
The UNT Digital Library
REMOVAL OF A RADIOACTIVE PRIMARY SODIUM PUMP OR A RADIOACTIVE PRIMARY COLD TRAP
Methods and procedures are described for removing a radioactive primary sodium pump or a primary cold trap with handling casks from the Hallam Reactor. (D.L.C.)
Date:
May 1, 1960
Creator:
Mallon, P.J.
Object Type:
Report
System:
The UNT Digital Library
Laboratory Investigation of Decontaminating Solutions for Primary Loop Decontamination in the New Production Reactor
An investigation was made of methods for decontaminating the primary loop of the New Production Reactor (NPR). Decontamination factors ranging from fifty to several thousand were obtained with several different combinations of cleaning solutions. In general, fission product activity was removed to a lower residual level than was activated corrosion product activity, and carbon steel was easier to decontaminate than was stainless steel. It was necessary to completely remove the oxide film from the metal surfaces to obtain adequate activated corrosion product decontamination. Descaling procedures were also satisfactory for decontaminating fission product and uranium dioxide contamination. (M.C.G.)
Date:
November 1, 1960
Creator:
Mendel, J. E.
Object Type:
Report
System:
The UNT Digital Library
Measurement of Coefficients of Reactivity. 0 EFPH. Core I, Seed 2. (T- 550132). Section 1
None
Date:
September 22, 1960
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
MARITIME GAS-COOLED REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR PERIOD ENDING, SEPTEMBER 30, 1960
The feasibility was studied and a cost estimate prepared of an experimental reactor to determine the operating characteristics of beryllia- moderated, gas-cooled systems wtthin a power limit of 10 Mw(t). The heat energy produced by the experimental reactor is to be dissipated in a heat dump. No machinery for production of power was to be provided. Other requirements were that the reactor should be capable of testing core types different from the current MGCR design, and the system should permit use of gases other than helium. It was further directed that the reactor should be designated BORE for Beryllium- Oxide Reactor Experiment. Reactor development work was mainly in connection with the BORE preliminary design. It was established that the most important information which could be provided by a 10 Mw(t) reactor experiment would be on performance of fuel elements and moderator bodies. This required that the experirment duplicate the power density in the fuel and moderator that would exist in the full size reactor and made it advisable to use full length fuel elements. This resulted in an unconventionally shaped core which is roughly cylindrical with the length more than twice its mean diameter. Studies continued on performance of fuel …
Date:
September 30, 1960
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
ON TWO-DIMENSIONAL FLUID MOTION THROUGH A SPOUT COMPOSED OF FOUR PLANE WALLS
The mapping function, the complex potential, and the equations for the streamlines and equipotential lines for the fluid motion through a spout were obtained. One nudiscussed. (auth)
Date:
October 17, 1960
Creator:
Yeh, G.C.K.
Object Type:
Report
System:
The UNT Digital Library
Evaluation of Buried Conduits as Personnel Shelters
Supersedes ITR-1421. Twelve large-diameter buried conduit sections of various shapes were tested in the 60- to l49-psi overpressure region of Burst Priscilla to make an empirical determination of the degree of personnel protection afforded by commercially available steel and concrete conduits at depths of burial of 5, 7.5, and 10 feet below grade. Essentially, it was desired to assure that Repartment of Defense Class I, 100psi and comparable radiations, and Class II, 50-psi and comparable radiations, protection is afforded by use of such conduits of various configurations. Measurements were made of free-field overpressure at the ground surface above the structure; pressure inside the structures; acceleration of each structure; deflection of each structure; dust inside each structure; fragmentary missiles inside the concrete structures; and gamma and neutron radiation dose inside each structure. All buried conduit sections tested provided adequate Class I protection for the conditions under which the conduits were tested. Standard 8-foot concrete sewer pipe withstood 126-psi overpressure without significant damage, minor tension cracks observed; standard 10-gage corrugated-steel 8-foot circular conduit sections withstood 126- psi overpressure without significant damage; and standard 10-gage corrugated- steel cattle-pass conduits withstood 149-psi overpressure without significant damage. Durations of positive pressure were from 206 to …
Date:
July 14, 1960
Creator:
Albright, G. H.; LeDoux, J. C. & Mitchell, R. A.
Object Type:
Report
System:
The UNT Digital Library
ARMY GAS-COOLED REACTOR SYSTEMS PROGRAM. GCRE-I HAZARDS SUMMARY REPORT. ADDENDUM III
The hazards evaluation was modified to reflect certain changes made to the equipment as a result of operating experience. These changes included: the addition of a startup interlock circuit; the modification of a startup interlock circuit; several minor modifications to the control rod actuators; and the addition of the tube-sheet cooling system. (M.C.G.)
Date:
May 1, 1960
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
75,000 KILOWATTS OF ELECTRICITY BY NUCLEAR FISSION AT THE HALLAM NUCLEAR POWER FACILITY
For presentation at ASCE Convention in Reno, Nevada on Thursday, June 23, 1860. A description of the Hallam Nuclear Power Facslity is presented. The history of the project, program participants, site description, component development program, reaetor building, reactor structure, reactor core, sodium systems, instrumentation and control, fuel and component handling, auxsilary sustems, special design features, and advantages of sodium graphite reactor systems are discussed. (M.C.G.)
Date:
January 1, 1960
Creator:
Gronemeyer, F.C. & Merryman, J.W.
Object Type:
Report
System:
The UNT Digital Library
METAL-TO-CERAMIC SEAL TECHNOLOGY STUDY. Final Technical Report, June 22, 1959 to September 22, 1960
None
Date:
October 1, 1960
Creator:
Cole, S. S., Jr.; Larisch, W. L.; Inge, J. E.; Styhr, K. H., Jr. & Cheatham, E.
Object Type:
Report
System:
The UNT Digital Library
THERMAL DESIGN OF THE MGCR CORE
The design information is presented in sections on core thermal performance, fuel elements, moderator, and control rods. (J.R.D.)
Date:
August 1, 1960
Creator:
Rogers, J.T. & Katz, R.
Object Type:
Report
System:
The UNT Digital Library
Thermoelectric Materials. Final Report, January 28, 1959-July 28, 1960
BS> A method for the measurement of thermal conductivities of electrically conducting materials at temperatures in excess of 1000 deg C with a high accuracy was devised. The spatial boron concentration gradient in boron- doped graphite to achieve maximum p-type thermoelectric output was established. The production of an n-type silicon carbide-graphite composit was studied. Theoretical studies produced a detailed picture of the effect of doping on the electronic properties of graphite. A method was developed for the preparation of rare earth nitrides in a good state of purity. Electrical studies of the materials produced showed that several of the compounds are semiconductors as had been predicted. (M.C.G.)
Date:
August 15, 1960
Creator:
Brechenridge, R. G.
Object Type:
Report
System:
The UNT Digital Library
Effects of the Maximum Credible Accident Relevant to the Design of the Containment Shell, Experimental Low-Temperature Process Heat Reactor Project
The effects of the maximum credible accident relative to the design of the containment shell are discussed. The maximum credible accident is defined. The thermal and hydraulic effects of the maximum credible accident on the reactor system were analyzed. The extent to which fuelrod cladding will melt was estimated. The amount of energy released from the reactor system by the escaping steam and water and by a possible chemical reaction was calculated along with the corresponding pressure rise inside the containment shell. The kinds, amounts, and total radioactivity of fission products released to the atmosphere of the containment shell after the core melts were predicted. (M.C.G.)
Date:
March 21, 1960
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Development of Liquid-Phase Sintering Techniques for Molybdenum Alloys. Final Report
An envelope-type microstructure produced by liquidphase sintering techniques was used to develop ductiIe molybdenum-base alloys for sodium-cooled fast reactor application. A total of 105 compositions was examined; 21 showed evidence of room-temperature ductility, and a number of other compositions appeared promising. The prerequisites for obtaining ductile liquid-phase sintered materials were demonstrated. The most ductile alloys produced are based on the Mo--Pd--Cu and Mo --W--Ni--Fe systems. Molybdenum-base compositions were developed which could be rolled to 90% reduction in thickness at room temperature. The compactibility of selected alloys with uranium at 750 deg C and liquid sodium at 650 deg C was studied. In both cases the presence of iron and nickel was found to be deleterious. Although alloys compatible with uranium were produced, the specimens exposed to liquid sodium all showed evidence of attack to varying degrees. Two compositions based on the Mo--W--Ni and W--Cr--Ni systems, respectively, appear to hold promise as potential canning materials for sodium- cooled fast reactor application. (auth)
Date:
November 10, 1960
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Periodic Radiation Survey of Reactor Plant Container and Components After Shutdown "F" Survey. Core I, Seed 1. Test Results (T-612076). Section 4
An investigation was conducted to obtain measurements of radiation levels inside the hemispherical heads of the 1-B heat exchanger. The radiation levels were measured at the handholes on two occasions with an interval of 640 hrs between them. A very large increase was noted and could be explained only by the possibility that the measurement survey points were not identical. (J.R.D.)
Date:
October 17, 1960
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
[Leon Breeden Scrapbook: 1960]
Scrapbook of materials including photographs, letters, newspaper clippings, performance programs, and various other notes and ephemera documenting the activities of the North Texas State College One O'Clock Lab Band during 1960.
Date:
1960~
Creator:
Breeden, Leon
Object Type:
Book
System:
The UNT Digital Library
[Photograph of Roy Williamson]
Photograph of Roy Williamson, a football player for North Texas State College. He wears his uniform and holds a football.
Date:
September 1960
Creator:
unknown
Object Type:
Photograph
System:
The UNT Digital Library
[Photograph of Football Player Bill Weaver]
Photograph of Football Player Bill Weaver, #61 in 1960. In the image Weaver is posing in a tackle stance for the camera. The rest of the image is blurred by camera movement.
Date:
September 1960
Creator:
unknown
Object Type:
Photograph
System:
The UNT Digital Library