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Aerodynamic Re-Entry Analysis. Task 2. Thermoelectric Generator Summary Report (open access)

Aerodynamic Re-Entry Analysis. Task 2. Thermoelectric Generator Summary Report

An analytical trajectory and aerothermodynamic analysis of a satellite containing a Task 2 thermoelectric generator was completed. A 300-statute mile circular polar orbit was used for this analysis and the launch was assumed to be from Vandenberg Air Force Base. Results of this study show that upon natural decay from a successful mission, the radio-cerium fuel will burn up in space at high altitude, thus only a very minor amount of radio cerium will be released to the stratosphere. A complete analyses of the fate of the radio-cerium fuel following various aborted launching attempts also was carried out. Charts summarizing the various assumed failures and locations of the fuel following failure are shown. A technical discussion of the methods used in performing the analysis is included in the report. (auth)
Date: December 27, 1960
Creator: Oehrli, R.
Object Type: Report
System: The UNT Digital Library
The Federal Flag Code Including Selected Questions and Answers (open access)

The Federal Flag Code Including Selected Questions and Answers

This report includes text of the Act, and of the Presidential Proclamation relating to the display of the flag at half-staff.
Date: November 27, 1968
Creator: Hutton, E. Jeremy
Object Type: Report
System: The UNT Digital Library
[News Script: Man Day] (open access)

[News Script: Man Day]

Script from the WBAP-TV/NBC station in Fort Worth, Texas relating a news story.
Date: September 27, 1968
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Object Type: Script
System: The UNT Digital Library
[News Script: Sports] (open access)

[News Script: Sports]

Script from the WBAP-TV/NBC station in Fort Worth, Texas relating a news story.
Date: October 27, 1968
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Object Type: Script
System: The UNT Digital Library
[News Script: Sports] (open access)

[News Script: Sports]

Script from the WBAP-TV/NBC station in Fort Worth, Texas relating a news story.
Date: October 27, 1968
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Object Type: Script
System: The UNT Digital Library
[News Script: Teen girls] (open access)

[News Script: Teen girls]

Script from the WBAP-TV/NBC station in Fort Worth, Texas relating a news story.
Date: November 27, 1968
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Object Type: Script
System: The UNT Digital Library
[News Script: Sr. Citizen's Fair] (open access)

[News Script: Sr. Citizen's Fair]

Script from the WBAP-TV/NBC station in Fort Worth, Texas relating a news story.
Date: October 27, 1968
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Object Type: Script
System: The UNT Digital Library
EGCR EXPERIMENTAL LOOPS, PRELIMINARY DESIGN REPORT (open access)

EGCR EXPERIMENTAL LOOPS, PRELIMINARY DESIGN REPORT

The EGCR was designed to accommodate up to four gascooled experimental loops plus several experimental fuel elements in the open core. Two of the loops will utilize 51/2-in.-O.D. stainless steel tubes passing through the core along an axis which is about 17 in. from the central axis of the core. The other two loops will utilize 91/2-in.-o.d. tubes about 68 in. from the central axis. Inherent safety in the design, facility design, primary loop design, auxiliary systems and equipment design, primary and secondary containment design, instrumentation and controls, and special operations are discussed. (M.C.G.)
Date: March 27, 1962
Creator: Neill, F.H. & Michelson, C.
Object Type: Report
System: The UNT Digital Library
Single Element Flow Tests for Type 3 (SM-2) Fuel Elements in SM-1, SM-1A, and PM-2A Cores (open access)

Single Element Flow Tests for Type 3 (SM-2) Fuel Elements in SM-1, SM-1A, and PM-2A Cores

Channel-to-channel flow distribution within Type 3 (SM-2, stationary and control rod fuel elements modified for use in the SM-1, SM1-1A, and PM-2A core support structures and control rod tubes was measured in single element flow testing. Plots of channel-to-channel flow distribution and element pressure drop at various element flow rates are given. Flow distribution for the top-orificed SM-1A and PM-2A stationary elements was within the plus or minus 12% deviation from element average utilized in previous thermal analyses of these cores. Testing of the bottom-orificed SM-1 stationary element and the SM-1, SM-1A, and PM-2A control rod assemblies showed flow distribution exceeded plus or minus 12% devation from average. Simple modifications to the SM-1 stationary element indicated the possibility of improvng fiow distribution in that element. (auth)
Date: November 27, 1961
Creator: Krause, P. S.
Object Type: Report
System: The UNT Digital Library
Thermal Stress Testing of Type 1 Fuel Plates (open access)

Thermal Stress Testing of Type 1 Fuel Plates

Thermal stress tests on Type 1, SM-1A Core II fuel ele-ment sections were performed to study plate distortion and determine its dependency on temperature distribution, temperature differential, initial flatness, and ripple length. Test results will be correlated with the analytical model and used to predict ripple growth in other plate-type fuel elements. The tests showed that ripple growth is dependent on initial flatness of the plate and that the characteristic shape of ripples is maintained at all temperature differentials: The tests also showed that the ripple growth rate for a ripple of 5 mil initial magnitude is approximately 0.12 mils/ deg F for a peak temperature differential of 103 deg F and that the apparent relationship between ripple net growth and length is 1.3 mil/in. of ripple for a peak temperature differential of 103 deg F. A permanent distortion of 2 mils for a complete temperature cycle from 0 to 103 to O deg F differential was found. The temperature profile across the plate width was found to affect the magnitude of ripple growth. (auth)
Date: June 27, 1962
Creator: Gebhardt, F. G.
Object Type: Report
System: The UNT Digital Library
Nuclear Analysis of Various Spert-III Critical Experiments (open access)

Nuclear Analysis of Various Spert-III Critical Experiments

Editor please delete 26456.<><DSN>16:026457<ABS>Work done in the P122 reactor control actuator area is summarized. Actuators were required to radially position the absorber blades in the core of the reactor. The P122C1 was a subsonic power plant and temperatures were low enough to permit the use of hydraulics in the actuator area. The program was reoriented and the power plant designated P122C3 which was a supersonic version of the folded flow power plant. The ambient temperature at maximum power was high enough to require pneumatic actuation of the control blades. The program was reoriented after two design iterations of the subsonic power plant. A test model of the actuating equipment and the entire linkage assembly was on hand and completed when the program was cancelled. The linkage was being redesigned for the supersonic application and special bearings were ordered for fabrication into the lower temperature rig. The actual mechanical concepts of the pneumatic actuator were under study when the program was cancelled. (auth)
Date: April 27, 1961
Creator: Paluszkiewicz, S.
Object Type: Report
System: The UNT Digital Library
AN ESTIMATE OF THE EFFECT OF NEUTRON-ENERGY SPECTRUM ON RADIATION DAMAGE OF STEEL (open access)

AN ESTIMATE OF THE EFFECT OF NEUTRON-ENERGY SPECTRUM ON RADIATION DAMAGE OF STEEL

The postulate that the average number of lattice displacements is directly proportional to the available energy is carried one step further; it is assumed that damage to steel (particularly in regard to brittle fracture) is proportional to the number of lattice vacancies that occur. The model, although crude, permits estimation of the relative damage resulting from differences in neutron spectra. The results can be used as a rough method of correcting damage data for the effect of the neutron-energy spectrum. Radiation damage calculations for steel, relative to those for a fission spectrum, were made for neutron spectra that result from fission neutrons penetrating water or graphite. The results were plotted as a function of effective distance from the fission source. From this plot it is possible to make a conservative estimate of the correction factor to apply to damage data obtained with different neutron spectra. (auth)
Date: July 27, 1962
Creator: Claiborne, H.C.
Object Type: Report
System: The UNT Digital Library
ISOPERIMETRIC AND OTHER INEQUALITIES IN THE THEORY OF NEUTRON TRANSPORT, II (open access)

ISOPERIMETRIC AND OTHER INEQUALITIES IN THE THEORY OF NEUTRON TRANSPORT, II

In a prevlous paper, some inequalities occurring in the one-veloclty theory of neutron transport with lsotropic scattering were derived. Some of the previous results are generalized to the case of linearly anisotropic scattering. (auth)
Date: February 27, 1962
Creator: Dresner, L.
Object Type: Report
System: The UNT Digital Library
EFFECTIVE CUTOFF ENERGIES FOR B, Cd, Gd, AND Sm FILTERS (open access)

EFFECTIVE CUTOFF ENERGIES FOR B, Cd, Gd, AND Sm FILTERS

Effective energy cutoffs have been calculated on an IBM7090 computer for Cd, Gd, Sm, and B filters as functions of filter geometry, the ratio of Maxwellian to epithermal flux (assumed to be 1/E), the lower energy limit of the 1/E flux, the energy corresponding to the Maxwellian most probable (modal) velocity and filter thickness. The geometrical configurations were spherical (which on the assumptions madc is equivalent to a beam flux case), cylindrical and slab. By the use of two or three different filters (Cd and Gd and perhaps Sm) it should be possible to detect resonances in the thermal to cutoff energy regions, in addition to measuring resonance integrals and thermial cross sections of unknown nuclides. (auth)
Date: July 27, 1962
Creator: Stoughton, R.W. & Halperin, J.
Object Type: Report
System: The UNT Digital Library
Specifications and Fabrication Procedures for Type 3 Fuel Elements (open access)

Specifications and Fabrication Procedures for Type 3 Fuel Elements

Process and product requirements to be met in the fabrication of Type 3 fuel elements are presented. The fuel elements specified consist of thin plates of a dispersion of highly enriched UO/sub 2/ and ZrB/sub 2/ in a stainless steel matrix which is clad with stainless steel on all surfaces. Quality assurance provisions are discussed. Process and material specifications and packaging and packing for shipment are described. Sample calculations and drawings are included. (M.C.G.)
Date: April 27, 1962
Creator: Edgar, E. C. & Clayton, H. R.
Object Type: Report
System: The UNT Digital Library
Temperature Coefficients of the Reactivity Measurement Facility (open access)

Temperature Coefficients of the Reactivity Measurement Facility

The temperature coefficient of the Reactivity Measurement Facility was found to be 49 plus or minus 1 mu k/ deg C (1 mu k = 10/sup -6/ DELTA k/k) in the range 15.4 to l7.8 deg C. The change in the net reactivity of a standard sample was --0.48 plus or minus 0.02, --0.66 plus or minus 0.03, and --0.78 plus or minus 0.02 mu k/ deg C in three measuring positions. These low values generally make temperature corrections insignificant. The above results are compared with previous determined values. This information developed in the RMF should be generally applicable to flux-trap-type reactors such as the Advanced Reactivity Measurement Facility (ARMF) and ARMF-ll, now under construction. RMF was dismantled in April 1962. (auth)
Date: July 27, 1962
Creator: Fast, E.
Object Type: Report
System: The UNT Digital Library
Comparison of SNAP-50/SPUR System With MHD, Brayton, Boiling Reactor and Thermionic Systems (open access)

Comparison of SNAP-50/SPUR System With MHD, Brayton, Boiling Reactor and Thermionic Systems

This report addresses the comparison of SNAP-50/SPUR System with MHD, Brayton, boiling reactor and thermionic systems.
Date: April 27, 1965
Creator: Allen, J. E.
Object Type: Report
System: The UNT Digital Library
The Angular Distribution of Fission Fragments From the Fast Neutron-Induced Fission of U-234 (open access)

The Angular Distribution of Fission Fragments From the Fast Neutron-Induced Fission of U-234

Submitted to Univ. of Tennessee, Knoxville. The fast neutron-induced fission cross section of U/sup 234/ was measured from threshold to 4-Mev neutron energy. A maximum of 1.26 barns was found at 850 kev followed by a minimum of 1.10 barns at 8050 kev. The angular ani-sotropy of the fragment distribution was measured for neutron energies from 400 kev to 4 Mev. Extrema in the ratio sigma /sub f//( sigma /sub f(90 deg ) were found at 500, 850, and 1050 kev; the distribution at 500 kev showing a maximum in the direction normal to the beam (side-wise peaking) while that at 850 kev showed a maximum along the beam direction. The distribution at 8050 kev showed forward peaking but to a lesser extent than for energies immediately higher or lower. The behavior was analyzed according to the theories of Bohr and Wheeler. The dip in cross section between 850 and 1050 kev is consistent with the suggestion of Wheeler that neutron competition in the decay of the compound nucleus enters with increased strength in this area. Vibration-rotational levels in U/sup 234/ beginning at 790 kev are known to exist and inelastic neutron scattering to these levels serves to depress the …
Date: August 27, 1962
Creator: Lamphere, R. W.
Object Type: Thesis or Dissertation
System: The UNT Digital Library

[Photograph 2012.201.B0314.0015]

Photograph taken for a newspaper owned by the Oklahoma Publishing Company. Caption: "Secretary of the American Indian Center Inc."
Date: January 27, 1968
Creator: Hill, Ron
Object Type: Photograph
System: The Gateway to Oklahoma History

BASEMENT BOX 67.0194

Photograph taken during daylight of firefighters with hoses and firetrucks working to manage a fire. Caption: "The spectacular fire destroyed nearly a block of business buildings and caused damage expected to approach $1 million."
Date: January 27, 1964
Creator: unknown
Object Type: Photograph
System: The Gateway to Oklahoma History

[Photograph 2012.201.B0223.0215]

Caption: "Oklahoma City police held a 7 1/2 foot Boa constrictor in custody for a while today. When officers spotted the serpent, it was wrapped around a man who was later booked as W. A. Chickanoka of Glasgow, Ky. The man was arguing with a clerk at a downtown hotel, trying to convince the clerk that he had a room reservation. Chickanoka, who also called himself "Wachickanoka, King of the Snakes," was booked for disorderly conduct. He posted $20 bond and was released. The snake king was wearing a tuxedo and stovepipe hat when he was arrested."
Date: July 27, 1968
Creator: Miller, Joe
Object Type: Photograph
System: The Gateway to Oklahoma History

[Photograph 2012.201.B0228.0515]

Photograph taken for a story in the Oklahoma Times newspaper. Caption: "A former Oklahoma Cityan is co-author of a new book that tells young people how to get into show business."
Date: January 27, 1964
Creator: unknown
Object Type: Photograph
System: The Gateway to Oklahoma History

[Photograph 2012.201.B0317.0195]

Photograph taken for a story in the Daily Oklahoman newspaper. Caption: "PINK, PAISLEY and pretty" is the capsule description of the supper dance honoring debutante Mary Lynn Duncan."
Date: August 27, 1966
Creator: Albright, Bob
Object Type: Photograph
System: The Gateway to Oklahoma History

[Photograph 2012.201.B0320.0009]

Photograph taken for a story in the Oklahoma Times newspaper.
Date: October 27, 1969
Creator: Miller, Joe
Object Type: Photograph
System: The Gateway to Oklahoma History