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Shock Hydrodynamics of an Exploding Steam Pressure Vessel : Final Report

Description: 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: unknown
Creator: Porzel, F. B.
Partner: UNT Libraries Government Documents Department
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The Preliminary Shield Design for the 50 MW Commercial Reactor

Description: 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: unknown
Creator: Bagley, R. O., Jr.
Partner: UNT Libraries Government Documents Department
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Primary Shielding Calculations on the IBM 650 (ROC Codes)

Description: 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: unknown
Creator: Rosen, S. S.; Oby, P. V. & Caton, R. L.
Partner: UNT Libraries Government Documents Department
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IBM 650 Computer, Program Number 755, Collation of ROC Code Output

Description: 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: unknown
Creator: Stueck, C. J.
Partner: UNT Libraries Government Documents Department
open access

Reactivity of Substitution Elements

Description: A method is sought for predicting the reactivity differences between fuel elements attached to control absorbers and fixed fuel elements
Date: unknown
Creator: Murray, R. L., Dr.
Partner: UNT Libraries Government Documents Department
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Rolling and Welding Type 430M Tubes to Stainless Steel Overlaid Carbon Steel Tubesheets

Description: 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: unknown
Creator: Bennett, R. W.; Meister, R. P. & Kerton, R. J.
Partner: UNT Libraries Government Documents Department
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Paper for Glasgow Conference on Nuclear Physics: Cosmotron Production of Heavy Mesons

Description: One might expect that the Cosmotron would offer certain advantages over cosmic rays for the study of heavy unstable particles; provided, of course, that it can produce them. In the first place, the conditions under which they are produced could be controlled to a considerably greater extent. In the second place, it might be possible to arrange conditions under which they would be observed more abundantly, an actual beam of heavy mesons being the ideal situation.
Date: July 1954
Creator: Thorndike, A. M.
Partner: UNT Libraries Government Documents Department
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A summary of drag results from recent Langley full scale tunnel tests of Army and Navy airplanes

Description: Report presenting the results of a drag investigation of twelve military airplanes in order to increase their speed. The main purpose of the report is to point out undesirable aerodynamic features as a guide to airplane designers. Results regarding the power-plant installation, installations in wings, empennages, armament, canopies, and radio antenna are provided.
Date: February 1945
Creator: Lange, Roy H.
Partner: UNT Libraries Government Documents Department
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Independent Counsel Law: Derivation of Major Changes to Provisions

Description: From Summary: "This report traces the changes and derivation of the major amendments to the provisions of federal law authorizing the appointment of what is now called an "independent counsel."
Date: February 22, 1999
Creator: Maskell, Jack
Partner: UNT Libraries Government Documents Department
open access

INSITE Information System Data Report

Description: This data report is intended to familiarize the INSITE system user not only with the data within the system, but also with the systematics of microfiche selection.
Date: April 1978
Creator: U.S. Nuclear Regulatory Commission. Site Designation Standards Branch.
Partner: UNT Libraries Government Documents Department
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Uranium Occurrences, Fall River Area, Clear County, Colorado [Fiche]

Description: This report describes the Fall River Area that was examined for favorable areas between known occurrences of pitchblende at Quartz Hill and at Lawson.
Date: October 16, 1951
Creator: Smith, Loren E. & Baker, Kenneth E.
Partner: UNT Libraries Government Documents Department
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Airborne Gamma-Ray Spectrometer and Magnetometer Survey, North/South Tieline Airborne Survey: Final Report, Volume 1

Description: Report documenting results of an airborne high-sensitivity gamma-ray spectrometer and magnetometer survey of the 99-degree longitudinal line from the Canadian to the Mexican border in the U.S., including data acquisition methods, a summary of data and outline of data presentation, area geology, and interpretation of results.
Date: May 1981
Location: None
Partner: UNT Libraries Government Documents Department
open access

Dispersion Strengthening of Iron-Aluminum Base Alloys: A Feasibility Study

Description: The feasibility of improving the mechanical properties at 1700-1800°F of oxidation-resistant Fe-Al-Cr alloys by means of a refractory dispersion has been explored. A literature search was conducted, preliminary experimental determinations of properties of the alloy and its oxides were carried out, and certain mathematical relations between dispersion characteristics and metallurgical variables were derived. The results indicate that the alloys can be strengthened sufficiently by using a dispers… more
Date: December 27, 1960
Creator: King, Blake
Partner: UNT Libraries Government Documents Department
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ORR Startup Accident and Cooling Flow Coastdown Analog Analysis

Description: Startup accident and pump run-down on the ORR have been simulated on the Reactor Controls Analog Facility. At full flow the 150% level scram (45 Mv) easily terminates the startup accident before the metal temperature gets above 180°F. For very low flows typical of criticality runs, temperature coefficients turn the excursion before it reaches 150% of full power, and temperatures climb to boiling, a potentially hazardous condition. (This same behavior can occur at full flow is the power is incr… more
Date: January 4, 1961
Creator: Stone, R. S. & Colomb, A. L.
Partner: UNT Libraries Government Documents Department

Water Treatment in Aqueous Homogeneous Reactors, Experience in HRE-2

Description: A method for water treatment has been developed for corrosion protection in the steam-water cycle of Homogeneous Reactor Experiment No. 2. The use of potassium phosphates for pH control, hydrazine for oxygen removal, and limitation of chlorides in the boiler water to less than 1 ppm has resulted in trouble-free operation of the steam system from December 1957 to December 1960.
Date: unknown
Creator: Neumann, P. D.
Partner: UNT Libraries Government Documents Department
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Summary of Runs 1, 2, and 3 in High-Temperature, High-Pressure Titanium Loop

Description: Simulated reactor fuel solutions were circulated at temperatures as high as 365°C in a small titanium pump loop. A hydroclone separator separated heavy phases formed at high temperatures. As the temperature of the solution was increased beyond the two-liquid-phase temperature (327°C), the salt concentration of the light phase decreased and the acid concentration increased. The mole ratios of uranium to sulfate, uranium to copper, and uranium to nickel in the light phase decreased in the same pr… more
Date: January 6, 1961
Creator: Griess, J. C.; Baker, J. M. & Savage, H. C.
Partner: UNT Libraries Government Documents Department
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Bremsstrahlung Absorption Measurements from Sr^90 TiO3

Description: The absorption in lead of Bremsstrahlung X radiation from a Sr^90 TiO3 pellet in the proximity of Hastelloy "C" was measured. The tenth value layer of the more energetic components of the X-ray continuum was determined to be 1.60 inches.
Date: January 13, 1961
Creator: Butler, T. A. & Pierce, E. E.
Partner: UNT Libraries Government Documents Department
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