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Atomic Energy Commission Reports
5,449
NACA Research Memorandums
5,157
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4,107
United States Geological Survey Reports
2,774
GJBX
2,662
United States Department of Energy Grand Junction Office Reports
2,433
United States Bureau of Mines Reports
1,521
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1,438
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1,423
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32,815 Matching Results
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Two-Group Multiregion Axial Window Shade Calculation on the IBM 650
The code is a nine-region, two group finite difference calculation in slab geometry for the basic IBM 650 with a 2000 word storage capacity and one Type 533 unit. The code solves the steady-state two-group equation with fast and thermal fission.
Date:
March 29, 1957
Creator:
Fairbanks, F. B.
Object Type:
Report
System:
The UNT Digital Library
APPR-1 Control Rod Experiments and Calulations
The methods used to treat partially and fully inserted APPR-1 control rods are described
Date:
March 6, 1957
Creator:
Fairbanks, F. B. & Gallagher, J. G.
Object Type:
Report
System:
The UNT Digital Library
APPR-1 Hot Channel Factors: Re-Evaluation on the Basis of Manufacturing Experience and Zero Power Experiments
On the basis of recent experiment with APPR-1 fuel elements manufactured by ORNL,hot channel factors have been derived from the observed dimensional deviations
Date:
May 6, 1957
Creator:
Brondel, J. O.
Object Type:
Report
System:
The UNT Digital Library
Effect of APPR-1 Control Rod Acceleration after Scram on Startup Accident
In the operation of the APPR-1 the most dangerous condition exists at cold startup. Therefore the behavior of the APPR-1 in a startup accident with a rod acceleration of 0.4 g after scram is considered
Date:
April 23, 1957
Creator:
Gallagher, J. G. & Silks, T. M.
Object Type:
Report
System:
The UNT Digital Library
Appendix C. Qualified Data Plots
Plots of qualified data from Reactivity Initiated Accident (RIA) Series 1-4 fuel behavior test conducted at the Idaho National Engineering Laboratory in Idaho Falls, Idaho.
Date:
September 1984
Creator:
Cook, Beverly A. & Martinson, Zoel R.
Object Type:
Dataset
System:
The UNT Digital Library
Geologic Reconnaissance of the Southwest Flank of the Zuni Uplift, New Mexico
Report presenting the results of a survey in the southwest segment of the Zuni Uplift sedimentary formations. The report includes figures and plates that provide an overview of physical geography in the area, as well as economic geography, including mineral deposits.
Date:
August 1955
Creator:
Konigsmark, Ted
Object Type:
Report
System:
The UNT Digital Library
[Average Record Data Listings for Nulato Quadrangle]
Average record data listings taken during aerial gamma-ray and magnetic surveys of the Nulato quadrangle in Alaska.
Date:
May 9, 1980
Creator:
Aero Service (Firm)
Object Type:
Dataset
System:
The UNT Digital Library
Summary of the Research Progress Meeting
Technical report includes three reports of research progress: 1) Range Measurements on 190 Mev Deuterons, M. Stephan; 2) Meson measurements, C. Lattes; and 3) N-P Scattering, R. Christian.
Date:
April 22, 1948
Creator:
Wakerling, R. K. (Raymond Kornelious), 1914-
Object Type:
Report
System:
The UNT Digital Library
Uranium-235 Abundance by Gamma Spectrometry
Techniques are described for determining U-235 abundance by measurement of the intensity of 0.18 Mev gamma radiation. One method involves measurement of the ratio of the intensity of 0.18-Mev radiation to that of 0.1 Mev radiation. The preferred technique consists of chemical separation of uranium followed by direct counting of 0.18-Mev photons. Application has been made in analysis of uranium samples of abundances in the range of 0.05% to 93%. Accuracy appears to be better than 3% if the abundance is between 0.7% and 100%. Findings in the self-absorption of 0.18 Mev radiation in uranium oxide are presented.
Date:
January 2, 1957
Creator:
Reynolds, S. A. & Eldridge, J. S.
Object Type:
Report
System:
The UNT Digital Library
The SNAP II Power Conversion System. Topical Report No. 4. Turbine Design and Testing
SNAP II is the designation for a 3 KW nuclear auxiliary power unit to be used in a satellite vehicle. The SNAP II system consists of a reactor heat source, a mercury Rankine engine and an alternator. A two stage, full admission, axial flow turbine was chose for the APU application. Design details and test results are presented in this report. This work was performed under a subcontract to to Atomics International as part of the Atomic Energy Commission Contract No. AT(11-1)-GEN-8.
Date:
January 18, 1960
Creator:
Poulos, Earnest N. & Forman, Edward R.
Object Type:
Report
System:
The UNT Digital Library
Time Variation of Thermodynamic Parameters of a Gas in the Region of a Shock Front : Progress Report III
The original goal of this investigation was to compare the thermodynamic characteristics of the gases in and behind the shock fronts in gases at initial pressures in the millimeter range and to compare these characteristics in the geometries of single and double discharges. The shock fronts were not visible, so it was not possible, at these pressures, to get visual data from the shock front itself. The parameters giving the properties of the gases were faces. Measurements made with an image converter camera (which is still in the development stage) agree well with these made with a photomultiplier tube. Differences are observed between the front velocities in the cases studied. These are of the order of 3 to 15 per cent. Considering the nature of the shot to shot fluctuations in the discharges and the inductance variation between the single and double discharges represent a physical difference. The mathematical treatment which says that two equal strength colliding with a wall behaves, has not been shown to be inadequate by this investigation. It was hoped that a stronger confirmation could be fien to the theory, but the accuracy of the data does not warrant it.
Date:
November 30, 1959
Creator:
Eastmond, E. John (Elbert John), 1915-; Hales, Richard Wayne, 1926-; Hoyt, G. D.; Baird, Ramon C.; Chowdhury, P. N. R. & Strong, William J
Object Type:
Report
System:
The UNT Digital Library
Refinements of the Theory of the Infinitely-Long, Self-Acting, Gas-Lubricated Journal Bearing. Interim Report
The lubrication equations for an arbitrary Newtonian fluid are derived directly from the general equations for conservation of mass, momentum, and energy. From the lubrication equations an inequality is obtained for the internal film temperature rise, after which the isothermal film equations are derived. Then, for perfectly-aligned self-acting journal bearings, a conservation equation is obtained. For gas bearings this condition gives: [formula] constant along the axis of the bearing. Application of this condition to the infinitely-long gas bearing gives more accurate pressure solutions for this case. The Katto-Soda form of the differential equation for the infinitely-long bearing is solved by a series expansion in the eccentricity ratio, the first terms of which give the original, approximate Katto-Soda solution. In addition, solutions obtained numerically by digital computations are presented in graphical and tabular form for eccentricity ratios from 0 to 0.9 and compressible bearing parameter [formula]. Design charts based on these calculations are provided.
Date:
January 1960
Creator:
Elrod, Harold G., Jr.
Object Type:
Report
System:
The UNT Digital Library
Attempts to Delineate Inborn Anemias in Mice. Progress Report and Fifth Renewal Proposal, Report Period: January 10, 1959-January 31, 1960. Renewal Period: May 1, 1960-April 30, 1961
During the past year, three papers covering results of a major series of experiments on intergenotype of blood-forming tissue have appeared, demonstrating successful implantation of isologues normal cells in anemic hosts, permanently correcting their genetic defect in hematopoiesis, both with and without irradiation of the host. Heavy host irradiation was shown ineffective as preparations for implantation of homologous cells of widely different antigenic types.
Date:
February 16, 1960
Creator:
Russell, Elizabeth Shull, 1913-2001
Object Type:
Report
System:
The UNT Digital Library
A Survey of Non-Fuel-Bearing Materials for the Marine Gas-Cooled Reactor
Results of an initial examination of non-fuel-bearing materials for the Marine Gas Cooled Reactor are presented. Areas given specific attention include structural and cladding materials and graphite moderator. Other areas not included because of classification include zirconium hydride moderator and control materials. In each report section, available pertinent information is summarized and a plan for future work is given.
Date:
May 1, 1958
Creator:
Bokros, J. C.; Dijkstra, L; & Merten, U.
Object Type:
Report
System:
The UNT Digital Library
Progress letter No. 11 for January 1, 1960 through January 31, 1960
A stainless steel autoclave for superheated water corrosion test was installed and "conditioned". Tests were begun to investigate the feasibility of densifying slip cast stainless steel by means of liquid phase sintering. Attempts to prepare tubular fuel elements by vacuum forming were resumed. Although thick-walled vacuum formed casting have been sintered on the aluminum mandrels without cracking, this has not yet been accomplished with the think sections of interest.
Date:
February 15, 1960
Creator:
Baron, Edeard H.
Object Type:
Report
System:
The UNT Digital Library
Shock Hydrodynamics of an Exploding Steam Pressure Vessel : Final Report
Initially issued as a brief survey of the shock problems associated with an assumed failure of a pressurizer vessel in a vapor container, this paper contains more detailed calculations and considerations of the analysis present in the original study.
Date:
November 25, 1955
Creator:
Porzel, F. B.
Object Type:
Report
System:
The UNT Digital Library
The Preliminary Shield Design for the 50 MW Commercial Reactor
The investigation in this report were conducted to determine the required shielding to reduce radiation to a workable level, to determine the heeating in the various core components so coolant flow rates could be determined, and to determine the thermal stress and temperature distribution in the structural and load bearing members.
Date:
December 18, 1958
Creator:
Bagley, R. O., Jr.
Object Type:
Report
System:
The UNT Digital Library
Primary Shielding Calculations on the IBM 650 (ROC Codes)
In order to calculate the gamma dose rates in the primary shielding of thermal reactors, four programs were written for thew IBM 650 computer.
Date:
October 15, 1958
Creator:
Rosen, S. S.; Oby, P. V. & Caton, R. L.
Object Type:
Report
System:
The UNT Digital Library
Thermal Design Criteria for APPR Pressurized Water Reactors
The following criteria have been established for thermal design of APPR pressurized-water reactors in this study
Date:
November 26, 1958
Creator:
Love, J.
Object Type:
Report
System:
The UNT Digital Library
Material Specifications for APPR-1 Core II Control Rod Fuel Elements and Absorber Sections
The specifications reported in this study are based on the results of development performed at Oak Ridge National Laboratory under the supervision of the Metallurgy Division.
Date:
December 30, 1958
Creator:
Edgar, E. C. & Robertson, R. D.
Object Type:
Report
System:
The UNT Digital Library
Lovely-1, Program No. 55, Thermal Analysis on the IBM 650
This program is intended to be utilized for the establishment of flow requirements of a tailored flow core.
Date:
November 26, 1958
Creator:
Love, J. D. & Stueck, C. J.
Object Type:
Report
System:
The UNT Digital Library
IBM 650 Computer, Program Number 755, Collation of ROC Code Output
Using the output of programs 653 and 654, each card of which contains the dose information for one dose point at one energy, program 655 produces the sum of the dose values of all energies for one dose point
Date:
December 19, 1958
Creator:
Stueck, C. J.
Object Type:
Report
System:
The UNT Digital Library
Reactivity of Substitution Elements
A method is sought for predicting the reactivity differences between fuel elements attached to control absorbers and fixed fuel elements
Date:
January 19, 1959
Creator:
Murray, R. L., Dr.
Object Type:
Report
System:
The UNT Digital Library
Rolling and Welding Type 430M Tubes to Stainless Steel Overlaid Carbon Steel Tubesheets
In the fabrication of the steam generator on APPR-1A it was considered necessary to roll the Type 430M tubes into carbon steel tube-sheets. The rolled joint was a necessary precaution to prevent secondary water from contacting the stainless steel weld.
Date:
February 16, 1959
Creator:
Bennett, R. W.; Meister, R. P. & Kerton, R. J.
Object Type:
Report
System:
The UNT Digital Library