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Technical Report Archive and Image Library
985
Office of Scientific & Technical Information Technical Reports
948
National Advisory Committee for Aeronautics Collection
639
Texas Attorney General Opinions
204
USGS Topographic Map Collection
166
TRAIL Microcard Collection
156
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43
Government Documents A to Z Digitization Project
21
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16
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7
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NACA Research Memorandums
335
NACA Technical Notes
275
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141
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84
University of California Radiation Laboratory Reports
62
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55
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45
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37
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33
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27
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THE (5-PHENYL-2-OXAZOLYL)PYRIDINES AS FLUORESCENT pH INDICATORS. AN APPLICATION TO CHEMICAL RADIATION DOSIMETRY
The three isomeric (5-phenyl-2-oxazolyl)pyridines have been shown to be sensitive fluorescent pH indicators which show a pronounced change to increased visible fluorescence as the pH is lowered. Absorption and fluorescence spectral data and pK values are given. Selective excitation of fluorescence from the conjugate acid in the presence of the free base was found possible. The sensitivity of the 4-isomer was demonstrated to be adequate for determining the small amounts of acid produced in certain chemical dosimeter systems. (auth)
Date:
August 1, 1958
Creator:
Ott, Donald G.
Object Type:
Report
System:
The UNT Digital Library
17-keV x-ray output of plutonium
In the production of plutonium in a reactor, plutonium-238, 240, and 241 are formed as well as Pu{sup 239}. It is well known that the specific alpha activity of the plutonium varies as the percentages of these isotopes are changed. Kinderman, et al have worked out the relationship between isotopic content and MWD/ton exposure. Their findings are reported in this document.
Date:
November 5, 1958
Creator:
McCall, R. C. & Bernard, R. M.
Object Type:
Report
System:
The UNT Digital Library
100-Mw Nuclear Power Plant Utilizing a Sodium Cooled, Graphite Moderated Reactor
The conceptual design of a 100 Mw(e) nuclear power plant is described. The plant utilized a sodium-cooled graphite-moderated reactor with stainless- steel clad. slightiy enriched UO/sub 2/ fuel. The reactor is provided with three main coolant circuits, and the steam cycle has three stages of regenerative heating. The plant control system allows automatic operation over the range of 20 to 100% load, or manual operation at all loads. The site, reactor, sodium systems, reactor auxiliaries, fuel handling, instrumentation, turbine-generator, buildings. and safety measures are described. Engineering drawings are included. (W.D.M.)
Date:
February 28, 1958
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
100-N temporary construction line considerations
Present thinking and planning appears to be developing from the following factors as concern the 13.8 KV temporary construction power limit. 1. It is understood that the present intent is to supply 100-N operating requirements from a single stub source in the 230 KV loop. 2. The original thoughts were to obtain construction power over a 13.8 KV line from 151-D substation. 3. Construction load requirements are now less than originally planned since steam has been substituted for electrical drive of primary loop pumps and 5500 hp motor tests are no longer necessary. 4. An extreme emergency backup source for the K plants has always been of concern, although minimized in recent planning. It is desirable to review the temporary construction line requirements from a future operating viewpoint to determine if the line could be useful to the operating plants after completion of construction. It is highly desirable to provide T.C. power source from K plants rather than 151-D and then leave the line and breakers in place for future maintenance assistance and as extreme emergency backup to K plants.
Date:
December 30, 1958
Creator:
Mollerus, F. J.
Object Type:
Report
System:
The UNT Digital Library
224-UA continuous calciner trough examination
The continuous calciners at UO{sub 3} Plant are of a new design which was developed at HAPO and placed in service late in 1956. The heat transfer troughs are considered to be the most vulnerable parts of the calciners because of their high operating temperatures. Thermal stresses are calculated to be quite high, and when added to the direct mechanical stresses from powder load etc., come close to the limiting safe stress for stainless steel at the operating temperature. It is felt that trough failure will be progressive as a result of creep type distortion and cracks at stress concentration points. The higher the stress (and temperature), the more rapid the rate of failure will be. All possible steps have been taken to limit maximum trough temperature, rate of change, and variations from one part of the trough to another. These steps were not always successful and various troughs have been subjected to rather severe temperature shocks as well as high mechanical stresses due to agitator failures. Despite these difficulties, no signs of failure could be detected by visual inspection. It was decided, therefore, that a more complete examination should be made. This examination was made to determine the present …
Date:
March 10, 1958
Creator:
Kennedy, R. A.
Object Type:
Report
System:
The UNT Digital Library
450-Mev/C K$sup -$ and /Anti p/ Beams at the Northwest Target Area of the Bevatron Separated by the Coaxial Velocity Spectrometer
Enriched beams of 450 Mev/c K/sup -/ mesons and antiprotons have been produced by separation with the coaxial static electromagnetic velocity spectrometer. Characteristics of the final separated beams as observed in the 15- inch hydrogen bubble chamber are given together with a detailed description of the beam optics and apparatas. (auth)
Date:
June 1, 1958
Creator:
Horwitz, N.; Murray, J. J.; Ross, R. R. & Tripp, R. D.
Object Type:
Report
System:
The UNT Digital Library
1706-KER Coolant Test Facility Operations Manual
This procedure is intended to be used as: 1. An instruction and guide for operation of the KER loops. 2. To aid in familiarization and understanding of the general operation of the loops. 3. To prevent lost time due to errors in loop operation. The procedure is not meant to be completely comprehensive in all details of loop operation.
Date:
January 23, 1958
Creator:
Dulin, R. V.
Object Type:
Report
System:
The UNT Digital Library
Abernathy Quadrangle
Topographic map of a portion of Texas from the United States Geological Survey (USGS) project. The map includes towns, historic or notable sites, bodies of water, and other geologic features. Scale 1:62500
Date:
1958
Creator:
Geological Survey (U.S.)
Object Type:
Map
System:
The Portal to Texas History
Abilene
Topographic map of a portion of Texas from the United States Geological Survey (USGS) project. The map includes towns, historic or notable sites, bodies of water, and other geologic features. Scale 1:250000
Date:
1958
Creator:
Geological Survey (U.S.)
Object Type:
Map
System:
The Portal to Texas History
Abilene East Quadrangle
Topographic map of a portion of Texas from the United States Geological Survey (USGS) project. The map includes towns, historic or notable sites, bodies of water, and other geologic features. Scale 1:24000
Date:
1958
Creator:
Geological Survey (U.S.)
Object Type:
Map
System:
The Portal to Texas History
Abilene West Quadrangle
Topographic map of a portion of Texas from the United States Geological Survey (USGS) project. The map includes towns, historic or notable sites, bodies of water, and other geologic features. Scale 1:24000
Date:
1958
Creator:
Geological Survey (U.S.)
Object Type:
Map
System:
The Portal to Texas History
An Acceleration Schedule Control for Accelerating a Turbojet Engine and Its Use With a Speed Control
Memorandum presenting a study of an acceleration-limiting control on a turbojet engine in order to determine its feasibility as an acceleration control. A proportional-plus-integral type of controller was used in the investigation. Results regarding the one-loop control and two-loop control are provided.
Date:
May 12, 1958
Creator:
Gerus, Theodore F.; Powers, Albert G. & Heppler, Herbert J.
Object Type:
Report
System:
The UNT Digital Library
An Acceleration Schedule Control for Accelerating a Turbojet Engine and Its Use With a Speed Control
Memorandum presenting an acceleration-limiting control used on a turbojet engine to study the feasibility of its use as an acceleration control. A proportional-plus-integral type of controller was used in this investigation. Results regarding one-loop control and two-loop control are provided.
Date:
May 12, 1958
Creator:
Gerus, Theodore F.; Powers, Albert G. & Heppler, Herbert J.
Object Type:
Report
System:
The UNT Digital Library
Accelerations in Transport-Airplane Crashes
From Introduction: "A study of crash-impact survival in light airplanes is reported in references 1 and 2. A similar study for fighter airplanes is reported in reference 3. This report discusses crash-impact survival in transport airplanes."
Date:
February 1958
Creator:
Preston, G. Merritt & Pesman, Gerard J.
Object Type:
Report
System:
The UNT Digital Library
Accelerator Development Department Internal Report
In this report we present solutions of the design problem in which a system of quadruple lenses is required to carry a particle beam from given focal lines in the x and y planes to other given focal lines. Particular attention will be given to the case of the anastigmatic lens system which takes a beam from one focal point to another focal point. Since the general problem is almost impossibly complicated a simplification is introduced by breaking the lens system into two parts. The first part of the lens system is required to bring the initial beam to the state where it is parallel to the z axis in both planes. The second part carries the initially parallel beam to the required final condition. Each part will involve two quadrupoles so that the complete system will consist of four quadruples; usually, however, the field gradients in the second and third quadrupoles can be made identical so that those quadrupoles can be combined into one and the system becomes a three quadrupole system. The configuration of the lens element will be as shown in the figures below. These figures indicate also the general character of the beam path in the …
Date:
October 2, 1958
Creator:
Blewett, J. P.
Object Type:
Report
System:
The UNT Digital Library
Accidental Dispersion of Reactor Poisons and the Controlled Distance Required
Two types of hypothetical reactor catastrophe are considered. In the first of these, the Boiling Accident,'' it is assumed that a fraction of the radioactive material in a reactor is released to the atmosphere at a steady rate over a period of hours. In the second, the Puff Accident,'' it is assumed that the release of the radioactive material takes place instantaneously.'' The following concepts are used as measures of the hazard existing outside the controlled plant area. Danger Distance,'' defined as that distance beyond which the fission product cloud becomes so dilute that it cannot cause death; Probabiiity of Death per Capita per Accident,'' which is a measure of the hazard to any individual; and Expectation Number of Deaths per Accident.'' which is a statistical measure of the hazard to the entire off-site populace. Three mechanisms for each type of catastrophe were considered: direct irradiation from the fission product cloud, inhalation of the air in the cloud, and rainout from the cloud followed by irradiation from the ground. Failout is not considered. for it requires that a very energetic explosion be assumed. It is concluded that the size of the plant should be set by the hazard of irradiation …
Date:
March 1, 1958
Creator:
Menegus, R. L. & Ring, H. F.
Object Type:
Report
System:
The UNT Digital Library
Accidental Radiation Excursion at the Y-12 Plant, June 16, 1958: Final Report
This report describes the circumstances leading to the accident, attempts to reconstruct the nuclear reactivity conditions, and reviews the dosimetric means and results which were used to help determine the exposure of affected employees.
Date:
September 12, 1958
Creator:
Patton, F. S.; Bailey, J. C.; Callihan, A. D.; Googin, J. M.; Jasny, G. R.; McAlduff, H. J. et al.
Object Type:
Report
System:
The UNT Digital Library
Acoustic, thrust, and drag characteristics of several full-scale noise suppressors for turbojet engines
From Introduction: " Considerable analytical and experimental research has been done to find means of reducing the noise levels of the turbojet transports. Noise levels can be decreased by engine redesign to reduce the jet-exit velocity (ref. 1), proper flight-climb techniques (ref. 2), and the use of noise-suppression exhaust nozzles (refs. 3 to 5). The present report is concerned with the last method."
Date:
April 1958
Creator:
Ciepluch, Carl C.; North, Warren J.; Coles, Willard D. & Antl, Robert J.
Object Type:
Report
System:
The UNT Digital Library
The Activity of the Fission Products of U$sup 23$$sup 5$
Energy distributions and energy release rates of fission product gammas and energy release rates of the fission product betas are presented in tabular and graphical form, and the computation methods are outlined in detail. The data given for beta and gamma decay rates pertain directly to the thermal fission of U/ sup 235/. The possible effects of neutron energy spectra, other than thermal, and neutron flux level upon the fission product decay rates were examined, and the results are reported. The importance of bremsstrahlung caused by beta particles from fission products and the effect of photoneutron production due to the photonuclear reactions of the fission product gammas with D or Re were studied. Methods of evaluating these effects in the reactor are briefly described. (J.E.D.)
Date:
October 31, 1958
Creator:
Knabe, W. E. & Putnam, G. E.
Object Type:
Report
System:
The UNT Digital Library
An Addendum to a Parametric Study of the Gas-Cooled Reactor Concept
From introduction: "This report provides background information regarding the study results presented in the first volume of this report and provides information resulting from the studies made on the gas cooled reactor concept."
Date:
March 1, 1958
Creator:
Hanford Works
Object Type:
Report
System:
The UNT Digital Library
The adhesion of molten boron oxide to various materials
This report includes the description and results of an experiment evaluating the amount of adhesion existing between the liquid boron oxide and various materials used in engines.
Date:
April 1, 1958
Creator:
Witzke, W. R.
Object Type:
Report
System:
The UNT Digital Library
ADSORPTION FROM SOLUTION METHODS FOR SURFACE AREA MEASUREMENT
>The analytical procedures for wet adsorption methods for surface area measurements are described. (J.S.R.)
Date:
January 20, 1958
Creator:
Mills, G.F.
Object Type:
Report
System:
The UNT Digital Library
Advanced energy sources and conversion techniques. Volume 1. [35 papers]
This report addresses the advanced energy sources and conversion techniques.
Date:
November 1, 1958
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
An Advanced Engineering Test Reactor
A concpept for an advanced enineering test reactor is described. Thpe results of various investigations with regard to alternative design possibilitipes are presented. Retailed information is given rearding the nuclear and enineering calculations. (W.D.M.)
Date:
March 15, 1958
Creator:
Leyse, C. F.; Bertelson, P. C.; Chmielewski, W. S.; Delicate, W. S.; Francis, T. L.; Kornfeld, M. J. et al.
Object Type:
Report
System:
The UNT Digital Library