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The Snap Ii Power Conversion System Topical Report No. 12. Boiler Development (open access)

The Snap Ii Power Conversion System Topical Report No. 12. Boiler Development

The SNAP II boilers which were designed are summarized. As shown by test results from the three boilers which were tested, a continuous progress in design was achieved. These designs were based on test data from both the SNAP I and SNAP II programs. As the quantity of data increased, physical models describing the heat transfer process were developed. These physical models provide the necessary correlation parameters which permit the extension of existing data to advanced design. Preliminary test sections were designed on the assumption that an allvapor nmodel which ignores the presence of the liquid phase during forced convection boiling could be used to describe the process quantitatively. The conventional Dittus-Boelter equation was applied with the increase in the vapor flow along the tube being ascribed to liquid evaporation. The assumption led to a design that fell short by about an order of magnitude since the exit qualities were only in the range of 10%, far less than required for complete vaporization. As a result, a revision in the concept of the mechanics of boiling was found necessary and a theoretical analysis was formulated, based on a dry wall'' or dropwise'' type boiling phenomenon. The test results of the …
Date: July 17, 1961
Creator: Gido, R. G.; Koestel, A.; Haller, H. C.; Huber, D. D. & Deibel, D. L.
Object Type: Report
System: The UNT Digital Library
New Solutions of the Boltzmann Equation for Monoenergetic Neutron Transport in Spherical Geometry (open access)

New Solutions of the Boltzmann Equation for Monoenergetic Neutron Transport in Spherical Geometry

Solutions of the Boltzmann equation for monoenergetic neutron transport in spherical geometry are derived which are respectively singular and regular at the center of the sphere. A few specific partial singular solutions are presented. The regular solutions in spherical geometry are constructed by superposition of solutions in plane geometry which belong to the same k. Finally, the solutions are compared with their representations by a series of spherical harmonics. (D. L.C.)
Date: November 17, 1961
Creator: Kofink, W.
Object Type: Report
System: The UNT Digital Library
Analytical Chemistry of the Polyphosphates (open access)

Analytical Chemistry of the Polyphosphates

Additional data were obtained on the separation of linear polymers from cyclic polymers by precipitation with barium chloride. An unexpected peak was observed in the anion-exchange chromatography of a sodium poly-phosphate of n-bar average degree of polymerization) = 6, and the compound represented by this peak was isolated. An end-group titration of this compound by microtechnique proved unequivocally that it is a cyclic phosphate. Although the identification (number of phosphorus atoms per molecule) is not completed, evidence from its position in the elution graph by ion-exchange chromatography' and from paper chromatography indicate that it is probable pentametaphosphate, Na/sub 5/P/sub 5/O/sub 15/, or the boat form of tetrametaphosphate, Na/sub 4/P/sub 4/O/sub 12/. (P.C.H.)
Date: October 17, 1961
Creator: Rieman, W., III & Rothbart, H. L.
Object Type: Report
System: The UNT Digital Library
AN IBM 7090 FORTRAN PROGRAM FOR ASME UNFIRED PRESSURE VESSEL DESIGN AND PRELIMINARY COST ESTIMATION (open access)

AN IBM 7090 FORTRAN PROGRAM FOR ASME UNFIRED PRESSURE VESSEL DESIGN AND PRELIMINARY COST ESTIMATION

An IBM 7090 FORTRAN program was written for the preliminary design and cost estimation of unfired pressure vessels with or without a jacket. Both vessel and jacket designs conform to the 1959 ASME Boiler and Pressure Vessel Code, Section VIII, Unfired Pressure Vessels. Vessels and jackets from 5 in. pipe through 84 in. o.d. and 1/4 in. through 1 1/2 in. in metal thickness may be designed by this program as written. Total vessel cost is the sum of metal and fabrication costs, each on a weight basis. (auth)
Date: October 17, 1962
Creator: Prince, C. E. & Milford, R. P.
Object Type: Report
System: The UNT Digital Library
DETERMINATION OF COEFFICIENTS OF REACTIVITY 5532.3 EFPH. CORE I, SEED 1. Test Results (T-550132). Section 1 (open access)

DETERMINATION OF COEFFICIENTS OF REACTIVITY 5532.3 EFPH. CORE I, SEED 1. Test Results (T-550132). Section 1

None
Date: October 17, 1960
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Computer Technology and Congressional Operations: Selected References (open access)

Computer Technology and Congressional Operations: Selected References

This report serves as a series of citations indicating an increased interest in automatic data processing (ADP) within the United States Congress.
Date: July 17, 1969
Creator: Chartrand, Robert L. & Ayton, Mauree W.
Object Type: Report
System: The UNT Digital Library
Local Welfare Administrators' Comments On the "Welfare Crisis." (open access)

Local Welfare Administrators' Comments On the "Welfare Crisis."

This report discusses local welfare and it points out a wide range of opinions and proposals reflected in the discussions of proposals for improving or changing the exiting system.
Date: December 17, 1968
Creator: Malone, Margaret
Object Type: Report
System: The UNT Digital Library
[News Script: Blast] (open access)

[News Script: Blast]

Script from the WBAP-TV/NBC station in Fort Worth, Texas relating a news story.
Date: September 17, 1968
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Object Type: Script
System: The UNT Digital Library
[News Script: Paper dresses] (open access)

[News Script: Paper dresses]

Script from the WBAP-TV/NBC station in Fort Worth, Texas relating a news story.
Date: October 17, 1968
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Object Type: Script
System: The UNT Digital Library
Migratory Agricultural Labor: References to Federal Publications, Studies and Reports, 1959-1968 (open access)

Migratory Agricultural Labor: References to Federal Publications, Studies and Reports, 1959-1968

This report contains references to publications related to Migratory Agricultural Labor.
Date: January 17, 1969
Creator: Heslet, Mary R.
Object Type: Report
System: The UNT Digital Library
THE CYCLOTRON RESONANCE INSTABILITY WITH NEGATIVE MASS IONS (open access)

THE CYCLOTRON RESONANCE INSTABILITY WITH NEGATIVE MASS IONS

Both the effect of resonant coupling of ion cyclotron motion to electron plasma oscillations, as previously discussed by Harris, and the effect of a negative radial gradient in a magnetic mirror field, the so-called "negative mass'' effect, were combined in an approximate calculation for the threshold for electrostatic instability in DCX. The two mechanisms for instability were found to act more or less independently. (auth)
Date: October 17, 1961
Creator: Fowler, T.K. & Harris, E.G.
Object Type: Report
System: The UNT Digital Library
Periodic Waste Disposal System Material Balance Test. Core I, Seed 1. Test Results (T-641317). Section 3 (open access)

Periodic Waste Disposal System Material Balance Test. Core I, Seed 1. Test Results (T-641317). Section 3

An investigation was conducted to determine the adequacy of storage capacity and operating procedures of the waste disposal system during reactor cooldown for refueling. It was found that the waste storage capacity and the operating procedures were adequate. (J.R.D.)
Date: October 17, 1960
Creator: unknown
Object Type: Report
System: The UNT Digital Library
OPTIMUM FILL VOLUMES IN POT CALCINATION OF RADIOACTIVE WASTES (open access)

OPTIMUM FILL VOLUMES IN POT CALCINATION OF RADIOACTIVE WASTES

The 15,000 MW nuclear economy assumed for the long range study of pot calcination costs reported earlier was used as a basis for calculating optimum fill volumes. An algebraic expression was developed for cost as a functmon of the normalized radius of the central void space in a partially filled vessel. Minima of this expression were found for acmdmc and neutralized wastes in 6, 12, and 24in.-diameter vessels. Optimum fill volumes decreased as vessel diameter increased, varying for acidic wastes from 99.8% for 6-in.-diameter vessels to 92.5% for 24-in.diameter vessels. Decreases in costs by using optimum fill volumes instead of the 90% fill volume assumed for all cases in the long range study were small, the largest being an 8% decrease for neutralized wastes in 6- in.-diameter vessels. (auth)
Date: November 17, 1961
Creator: Perona, J.J.
Object Type: Report
System: The UNT Digital Library
METALLURGY DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING MAY 31, 1961 (open access)

METALLURGY DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING MAY 31, 1961

>Fundamental Alloying. Studies of crystal structures, reactions at metal surfaces, spectroscopy of molten salts, mechanical deformation, and alloy theory are reported. Long-Range Applied Metallurgy. A thermal comparator is described and the characteristic temperature of U0/sub 2/ determined. Sintering studies were carried out on ThO/sub 2/. The diffusion of fission products in fuel and of Al/sup 26/ and Mn/sup 54/ in Al and the reaction of Be with UC were studied. Transformation and oxidation data were obtained for a number of Zr alloys. Reactor Metallurgy. A large number of ceramic technology projects are described. Some corrosion data are given for metals exposed to impure He and molten fluorides. Studies were made of the fission-gas-retention Properties of ceramic fuel bodies. A large number of materials compatibility studies are described. The mechanical properties of some reactor materials were studied. Fabrication work was conducted to develop materials for application in low-, medium-, and high-temperature reactors or systems. A large number of new metallographic and nondestructive testing techniques are reported. Studies were carried out on the oxidation, carburization, and stability of alloys. Equipment for postirradiation examination is described. Preparation of some alloys and dispersion fuels by powder metallurgy methods was studied. The development of welding …
Date: August 17, 1961
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Experiment Facilities of the Oak Ridge Graphite Reactor (open access)

Experiment Facilities of the Oak Ridge Graphite Reactor

Up-to-date descriptive material and dimensional sketches of the ORNL Graphite Reactor and its experimental facilities are presented. (P.C.H.)
Date: August 17, 1962
Creator: Sheppard, S. D.
Object Type: Report
System: The UNT Digital Library
ON TWO-DIMENSIONAL FLUID MOTION THROUGH A SPOUT COMPOSED OF FOUR PLANE WALLS (open access)

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
Heavy-Ion Elastic Scattering (open access)

Heavy-Ion Elastic Scattering

The elastic scattering of C/sup 12/ ions from Ar, Fe, Ni, Ag/sup 107/ In, and Ta was measured as a function of angle, at a laboratory-system energy of 124.5 Mev with the Berkeley heavy-ion linear accelerator. The experimental equipment and techniques are discussed. The angular distributions show the same general behavior as previous heavy-ion elastic scattering experiments. The experimental data were analyzed with the semiclassical Blair model as modified by McIntyre. Very good agreement with experiment was obtained. The measurements were taken with 1% statistics in order to study the structure of the angular distributions in greater detail, because only by fitting the details in the structure was it possible to obtdin unambiguous sets of parameters. The parameters indicated a nuclear radius of 1.45A/sup 1/3/ x 10/sup -13/ cm, and a nearly constant surface thick ness of 1.6 x 10/sup -13/ cm. Total reaction cross sections were obtained. A rainbow-model analysis by Goldman of the data is given. Existing alpha - and heavy-ion scattering data were analyzed with the McIntyre model and compared with previous optical-model analyses of the same data. It was found that, by independent analysis, the two models give the same imaginary phase shifts for all partial …
Date: April 17, 1961
Creator: Alster, Jonas
Object Type: Thesis or Dissertation
System: The UNT Digital Library
NEUTRON PHYSICS DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 1, 1961 (open access)

NEUTRON PHYSICS DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 1, 1961

Fifty-seven papers and l7 abstracts of papers are presented in the report. Fifty two of the papers are abstracted separately; in addition, a single abstract is written to cover the section on Plasma Physics Theory, which contains 3 papers and 8 abstracts of papers. The two brief papers not abstracted separately are concerned with fast neutron detection, and homogeneous critical assemblies of 3%enriched UF/sub 4/-paraffin systems. (T.F.H.)
Date: November 17, 1961
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Determination of Maximum Permissible Irradiation of Type 3 (SM-2) Fuel Plates (open access)

Determination of Maximum Permissible Irradiation of Type 3 (SM-2) Fuel Plates

Two methods were used for predicting the maximum permissible burnup in type 3 (SM-2) fuel plates: use of analytical models and use of existing irradiation data on UO/sub 2/ stainless steel dispersion fuel plates. Results with two analytical models indicated that burnups above 100% U/35 are permissible. Comparison of the expected burnup with available irradiation data indicates that successful performance of type 3 replacement cores in SM-1, SM-1A, and PM-2A can be expected. (auth)
Date: March 17, 1962
Creator: Wilder, A. S. & Lelleman, R. W.
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 (open access)

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

[Photograph of Charles E. Wade]

Photograph of Charles E. Wade in Arlington. He sits at a desk, reading a book.
Date: January 17, 1962
Creator: unknown
Object Type: Photograph
System: The UNT Digital Library

[Photograph 2012.201.B0299.0195]

Photograph taken for a story in the Daily Oklahoman newspaper. Caption: "Cowboy third base duties are handled by senior Dale DeHart of Odesse, Texas."
Date: May 17, 1960
Creator: unknown
Object Type: Photograph
System: The Gateway to Oklahoma History

[Photograph 2012.201.B0051.1553]

Photograph taken for a newspaper owned by the Oklahoma Publishing Company. Caption: "One man died in this wrecked auto on Oklahoma City's east bypass early Friday morning. Nelson W. Eldred, 74, of 4402 N College, Bethany, was dead on arrival at Mercy Hospital after the car rammed into the rear of a truck."
Date: November 17, 1961
Creator: Traverse, Austin
Object Type: Photograph
System: The Gateway to Oklahoma History

[Photograph 2012.201.B0242.0642]

Photograph taken for a story in the Daily Oklahoman newspaper. Caption: "Named executive technical advisor in the refining department of Gulf Oil Corp., Ernest Cotton, above, is a native Oklahoman and graduate of the University of Oklahoma."
Date: December 17, 1969
Creator: unknown
Object Type: Photograph
System: The Gateway to Oklahoma History