Partner
UNT Libraries Government Documents Department
350
Oklahoma Historical Society
260
UNT Libraries Special Collections
153
Rosenberg Library
19
UNT Libraries
12
Hardin-Simmons University Library
9
Sterling Municipal Library
9
Brownwood Public Library
8
Cuero Public Library
8
Lamar State College – Orange
7
107 More
Collection
Office of Scientific & Technical Information Technical Reports
324
Texas Digital Newspaper Program
200
Oklahoma Publishing Company Photography Collection
186
KXAS-NBC 5 News Collection
128
Tocker Foundation Grant
89
Oklahoma Digital Newspaper Program
77
The Oklahoma City Times
22
University Photography Collection
22
Technical Report Archive and Image Library
21
Abilene Library Consortium
19
157 More
States
Decade
Month
Day
Language
1,012 Matching Results
Results open in a new window/tab.
Results:
1 - 24 of
1,012
next
Radioactive Waste Disposal System Periodic Radiation Monitoring Survey. Core I, Seed 1. Test Results (T-612075). Section 2
Radiation levels were determined at all permanently installed monitored points in the disposal area. Radiation levels were found to be generally higher than those measured during the previous test but within Health Physics limitations. (J.R.D.)
Date:
October 1, 1960
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
STUDIES IN MICROMERITICS. II. THE DEPOSITION OF PARTICLES IN CIRCULAR CONDUITS DUE TO THERMAL GRADIENTS
The deposition of particles from turbulent gas streams due to thermal gradients was predicted using a simplified flow medel. In the medels particle concentration was assumed constant in the turbulent region. The particle deposition velocity was taken to be the radial velocity of thermal - repulsion in the laminar sublayer. Temperature gradients in the laminar sublayer were calculated for constant wall temperature using the Reynoldss analogy. The loss magnilude of suspended particles from loss due to thermal deposition is not generally greats and is most important for submicron particles. (auth)
Date:
October 1, 1961
Creator:
Postma, A.K.
Object Type:
Report
System:
The UNT Digital Library
Nuclear Battery-Thermocouple Type Summary Report
The potential usefulness of approximately 1300 radioactive isotopes as a heat source for the thermoelectric generator was investigated. Only 47 were found to have the proper characteristics of high specific activity and usable haif-life combined with an easily absorbable radiation. These isotopes are discussed showing possible sources of supply, the hazards involved, and the expected performance. Three large Po/sup 210/ heat sources were designed and constructed (for battery use), including one for the SNAP III generator. One small Tl/sup 204/ test heat source was made by irradiation. Eight thermoelectric generators were developed and two of these were used as thermoelectric batteries. Theoretical equations for non-semiconductor thermoelectric materials and experimental measurements to verify the Thompson and Peltier effects are given. (auth)
Date:
October 1, 1960
Creator:
Blanke, B. C.; Birden, J. H.; Jordan, K. C. & Murphy, E. L.
Object Type:
Report
System:
The UNT Digital Library
Electrolytic Dissolution of Power Reactor Fuels in Nitric Acid
The electrolytic oxidation in nitric acid of stainless steel, zirconium, Zircaloy-2, zirconium- uranium alloy, aluminum, and uranium - molybdenum alloy was demonstrated on a laboratory scale. The rate of chemical dissolution of UO/ sub 2/ in nitric acid was measured. Corrosion of stainless steel by these dissolver solutions was measured and found to be negligible. Electrolytic dissolution was demonstrated to be a practical technique for the first step in processing fuel elements of several types of power reactors. (auth)
Date:
October 1, 1961
Creator:
Clark, A. T., Jr.; Meyer, L. H.; Owen, J. H. & Rust, F. G.
Object Type:
Report
System:
The UNT Digital Library
CORE A CRITICAL STUDIES FOR THE ENRICO FERMI ATOMIC POWER PLANT ON ZPR-III
A critical studies program for the Enrico Fermi Atomic Power Plant was run with the ZPR-III fast critical facility. The objectives of this program included determination of the U enrichment required for criticality, the effect of minor variations in core and blanket composition, reactivity coefficients, control and safety rod characteristics, power distribution, spectral indices, and the reactivity worth and wave shape of the oscillator rod. The experimental program was separated into two phases. The first phase involved investigatlona of a clean assembly, which was a simplified and homogenized core and blanket geometry constructed for ease of experimental manipulation and analysis. The second phase involved experiments on the engineered, or as-designed, core. This assembly included such engineering details as control and safety rod channels, core end gaps, and a precise reconstruction of the core outline. This provided detailed information on worths of control rods and fuel subassemblies, power distribution, and the effect of variations in core and end-gap dimensions. The application of critical experiment data to the determination of the Enrico Fermi reactor characteristics has established the U/sup 235/ enrichment for the fuel alloy, worths of fuel subassemblies, and the B/sup 10/ enrichment for the control and safety rods. In addition, …
Date:
October 1, 1962
Creator:
Branyan, C.E.
Object Type:
Report
System:
The UNT Digital Library
THE RELEASE OF Kr$sup 85$ FROM UO$sub 2$ IN ORR CAPSULES
In an attempt to determine the validity of the method of predicting the release of fission gases from U0/sub 2/ suggested recently by Cottrell et al., a series of calculations were made of the expected release of Kr/sup 85/ from prototype Experimental Gas-Cooled Reactor (EGCR) fuel capsule irradiated in the Oak Ridge Research Reactor (ORR). The computed values were then compared with measured values of the per cent Kr/sup 85/ released. In the calculations, the thermal conductivity of the U0/sub 2/ was assumed to be 0.028 w/cm- deg C in the temperature range from 700 to 1600 deg C, and in the absence of a precise knowledge of the helium gap, the cases of a 3-mil helium gas and no gap were treated. Values of the release-rate parameter (D) were estimated from BET surface areas of the U0/sub 2/ pellets. Results showed that the measured values of the per cent Kr/sup 85/ released generally fell within or close to the limits set by the 3-mil helium gap and no gap conditions. There was also a definite correlation between the measured values and the 3-mil gap condition when the clad temperature was about 700 deg C. When the clad temperature was …
Date:
October 1, 1961
Creator:
Scott, J.L.
Object Type:
Report
System:
The UNT Digital Library
Evaluation of Subsize Izod Specimen Designs for Determining the Notch Toughness of Zircaloy-2
Correlations were made on Zircaloy-2 Izod impact data and Charpy-V drop- weight data. Subsize Izod impact specimens of various geometries and notch configurations and standard ASTM Charpy-V specimens were prepared from bar and plate stock and tested. Drop-weight tests were also conducted and the NDT (nil- ductility transition) temperature was determined for 1/2 in. Zircaloy-2 plate. Results show that the impact properties of Zircaloy-2 are sensitive to hydrogen concentration, specimen and notch geometry, and specimen and notch orientation. No subsize specimen design was found which yielded impact curves similar to those obtained with standard Charpy-V notch specimens, but designs suitable for in- pile testing were found. It was found that Zircaloy-2 has the property of arresting a moving crack even at temperatures of --100 deg C and lower. (P.C.H.)
Date:
October 1, 1962
Creator:
Prislinger, J. J.
Object Type:
Report
System:
The UNT Digital Library
[News Script: Grand jury]
Script from the WBAP-TV/NBC station in Fort Worth, Texas relating a news story.
Date:
October 1, 1968
Creator:
WBAP-TV (Television station : Fort Worth, Tex.)
Object Type:
Script
System:
The UNT Digital Library
Migrant Labor Law and Relations: Selected References, 1960-1969
This report provides a bibliography of sources related to migrant labor law and relations that were published between 1960 and 1969.
Date:
October 1, 1969
Creator:
Guy, Kent
Object Type:
Report
System:
The UNT Digital Library
Chemical Technology Branch annual report, fiscal year 1967
None
Date:
October 1, 1967
Creator:
Bower, J. R.
Object Type:
Report
System:
The UNT Digital Library
Thermal-Stress and Strain-Fatigue Analyses of the MSRE Fuel and Coolant Pump Tanks
Thermal-stress and strain-fatigue analyses of the MSRE fuel and coolant pump tanks were completed for determining the quantity of coollng air required to obtain the maximum life of the pump tanks and to determine the acceptability of the pump tanks for the intended service of 100 heating cycles from room temperature to 1200 deg F and 500 reactor power-change cycles from zero to 10 Mw. A cooling-air flow rate of 200 cfm for the fuel pump tank was found to be an optimum value that provided an ample margin of safety. The coolant pump tank was found to be capable of the required service without air cooling. (auth)
Date:
October 1, 1962
Creator:
Gabbard, C.G.
Object Type:
Report
System:
The UNT Digital Library
Thermal Expansion and Phase Inversion of Rare-Earth Oxides
Thermal expansion and phase inversion measurements are reported on oxides of Sc, Y, La, and 12 lanthanide series elements up to 1350 deg C. (J.R.D.)
Date:
October 1, 1960
Creator:
Stecura, S. & Campbell, W.J.
Object Type:
Report
System:
The UNT Digital Library
A Simulation of the EGCR Steam Generator
An analog model of the EGCR steam generator was developed and operated on the ORNL analog computer as part of a program to simulate the operation and control of the EGCR reactor plant. Equilibrium operation and the transient response of the steam generator unit to system perturbations were studied. A simultaneous solution of the basic heat transfer equations representing the performance of the unit was obtained. The model was operated initially at steady- state conditions, and then perturbations were made to gas flow, gas inlet temperature, and steam throttle valve position. The response characteristics of the model during the transients were recorded. The steam generator gas outlet temperature showed a marked degree of insensitivity to changes in gas inlet temperature. The effect of gas flow changes on gas exit temperature was slightly more pronounced. The transient behavio-r of the unit was reasonable, and the model developed indicated satisfactory operation within the design range of 20 to l00% of full power. (auth)
Date:
October 1, 1961
Creator:
Yarosh, M.M. & Ball, S.J.
Object Type:
Report
System:
The UNT Digital Library
Economic Analysis of Replacement Cores for SM and PM Type Reactors
An economic analysis is presented for the fabrication of replacement cores for SM and PM type reactors, including analysis of various core types and core fabrication technologies. The analysis indicates that major savings are possible by utilizing Type 3 cores (40-mil plates, 25 wt% UO/sub 2/, welded assembly) in all SM and PM type reactors, and that significant savings are possible by multiple core procurement and reprocessing, and relaxation of cobalt and tantalum requirements in Type 347 stainless steel. (auth)
Date:
October 1, 1961
Creator:
Wilder, A. S.
Object Type:
Report
System:
The UNT Digital Library
Sodium Iodide and Sodium Iodide Crystals: Their Use in Scintillation Counting and Spectrometry. A Bibliography
References (297) were obtained from Applied Science and Technology Index, Chemical Abstracts, Dissertations in Physics, Nuclear Science Abstracts, and Science Abstracts, Section A. The period covered was from 1948 through l960. The arrangement is alphabetical by title; personal author and subject indexes are included. (P.C.H.)
Date:
October 1, 1961
Creator:
Kepple, R.R.
Object Type:
Report
System:
The UNT Digital Library
RESEARCH ON THE EFFECTS OF MAGNETIC FIELDS ON THERMIONIC POWER GENERATION. Progress Report No. 1
Research concerned with a theoretical and experimental study of magneto- thermionic power generation is reported. This concept promises a number of advantsges over conventional thermionic generators. Low pressure Cs diodes suffer from an undesirable size limitation, because selfinduced magnetic fields reduce current transmission and hence, efficiency. Although this effect does not arise in the small devices tested to date, it becomes important in building larger generators. Analysis indicates that this problem can be virtually eliminnted by the application of a longitudinal magnetic field. An experimental and theoretical study was initiated to verify the predicted magnetic field effects, and to examine their possible use in a-c generation. (auth)
Date:
October 1, 1961
Creator:
Schock, A. & Kunen, A.E.
Object Type:
Report
System:
The UNT Digital Library
SNAP 19 capsule low Reynolds number force test
None
Date:
October 1, 1966
Creator:
Stouffer, C.G.
Object Type:
Report
System:
The UNT Digital Library
RADIOACTIVITY OF NUCLEAR REACTOR COOLING FLUIDS
Methods were developed for analysis of cooling water for impurities, radioisotopes, etc., and experimental results are presented for the ORNL Research Reactor. The theory of nuclear reactions in a water-cooled reactor is discussed at length, and equations were developed which allows predictions of equilibrium conditions from nonequilibrium measurements. The equations were verified experimentally by work on the ORNL Research Reactor and can be extended to other reactors. The origins of Na/sup 24/, Cd, and fission product activities are discussed, and the possibility of fuel element rupture detection by delayed neutron measurements is considered. (D.L.C.)
Date:
October 1, 1961
Creator:
Ward, J.C.
Object Type:
Report
System:
The UNT Digital Library
An Evaluation of Reactor Concepts for Use as Separate Steam Superheaters
Various reactor concepts were compared for use as a separate superheater which could be added on to an advanced 300-Mwe reactor producing saturated steam. Fossil steam plant superheat temperatures were used as a criterion for selecting nuclear superheat temperatures. Therefore, the performance specified for the superheater was a minimum exit steam temperature of 566 deg C (1050 deg F) when supplied with saturated steam at either 7l atm (l050 psia) or l67 atm (2450 psia). A preliminary screening of ten different reactor concepts resulted in the selection of two for a detailed evaluation. These are a direct-cycle, watermoderated reactor, and an indirect-cycle, sodium-cooled reactor. The steam- cooled, water-moderated system is judged to have the best chance for initially reaching 566 deg C (l050 deg F), whereas, the indirect-cycle, sodiumcooled system is considered best for subsequent advances to exploit the more efficient, high- pressure steam reheat cycles. A design concept was selected for each of the reactors to establish a basis for the detailed evaluations and comparisons. The technical evaluation of the two concepts shows that the sodium-cooled, indirect- cycle superheater can realize a significant reductlon in the gross plant heat rate STA0.6097 to 0.5404cal/watt-sec (87l0 to 7720 Btu/kwh)! by use …
Date:
October 1, 1961
Creator:
Lennox, D. H.; MacFarlane, D. R.; Brubaker, R. C.; Martinec, E. L.; Rohde, R. R.; Toppel, B. J. et al.
Object Type:
Report
System:
The UNT Digital Library
Chemical Technology Branch, Annual Report, Fiscal Year 1968
None
Date:
October 1, 1968
Creator:
Bower, J. R.
Object Type:
Report
System:
The UNT Digital Library
ARGONNE NATIONAL LABORATORY PUBLICATIONS, JULY 1, 1961-JUNE 308 1962
A publications list, incorporating a subject index was compiled by machine methods. The publications covered are those originating at Argonne but published elsewhere. The list is arranged alphabetically by author's names and covers the period from July 1, 1961 through June 30, 1962. The subject index is a key word in context index using the title. (M.C.G.)
Date:
October 1, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Chemical Technology Division Unit Operations Section Monthly Progress Report, April 1962
Bubble size measurements in the foam column showed that a spinnerette with 50 mu holes gave a nearly normal distribution of bubbles sizes while a coarse fritted glass gas sparger had a tail of large bubbles which did not fit the normal curve. A set of equations solvable by a finite difference technique are presented which completely describe the irreversible reaction rate of H/sub 2/ or CO with a fixed bed of CuO pellets. Radiation damage tests are in progress to evaluate plastics for the Transuranium program. All dejacketed SRE Core I U fuel slugs were reeanned and shipped to Savannah River. Installation of the shear-leach complex is complete. The shortest practical length into which a tubular fuel element assembly may be sheared appears to be 1/2 in. Tests showed difficulties with shearing assemblies containing tube sheets. The stepped shear blade used for Mark I prototype fuel elements produced chunks of porcelain filled Yankee prototypes. Flow capacities of nozzle plate pulsed columns operated under dilute Purex fiowsheet conditions were determined. Fuel pins made with compacted sol-gel ThO/sub 2/ and U/sup 235/ were irradiated without difficulty to 17,000 Mwd/t. Routine operation of the rotary denitrator to give ThO/sub 2/ product was …
Date:
October 1, 1962
Creator:
Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Object Type:
Report
System:
The UNT Digital Library
TERMINAL REPORT ON THE BOILING SLURRY REACTOR EXPERIMENT (SLURREX). (Mockup Hydraulic Experiments)
None
Date:
October 1, 1961
Creator:
Lokay, J. D.
Object Type:
Report
System:
The UNT Digital Library
PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING SEPTEMBER 1961
Progress is reported in the development and evaluation of reactor materials and components, fuel and fuel-element development studies, growth of UO/ sub 2/ single crystals, radioisotope and radiation applications, corrosion studies of the fluoride-volatility process, assistance to the CANDU Reactor program, radiation effects studies of MGCR and SM-2 fuel materials, gas-cooled reactor program developments, corrosion of thorium and uranium under storage conditions, and gas-pressure bonding of beryllium-clad elements. (B.O.G.)
Date:
October 1, 1961
Creator:
Dayton, R.W. & Tipton, C.R. Jr.
Object Type:
Report
System:
The UNT Digital Library