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19,287 Matching Results
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1. K+ Charge Exchange - Search For K+ Charge Exchange
An experiment was designed utilizing a charge-exchange reaction to study the decay and interactions of the neutral K mesons produced. The experiment produced no events that could be interpreted as either the decay or interaction of neutral K mesons. The nature of the experiment and the possible explanations of this unexpected result are presented in this paper.
Date:
July 29, 1959
Creator:
Birge, Robert W.; Courant, Hans J.; Lanou, Robert E., Jr. & Whitehead, Marian N.
System:
The UNT Digital Library
1. Summary of Runs, s56, 57, 73, 74, 78, 79, 80, 87, 88, 89 in Which Slurries Circulated at 300 C in 100-a Loops Caked or Accumulated on Pipe Walls. 2. Summary of Runs T-52 Through T-75 in Which a Bypass Line Was Used in Parallel With Main Circulating Loop
None
Date:
November 16, 1956
Creator:
Kitzes, A. S.; Gallaher, R. B.; McLaughlin, C. A. & Wichner, R. P.
System:
The UNT Digital Library
3 Plant Radiation Study Interim Report #5- Part II Data on Gamma Shielding of Special Plutonium Samples
The calculation of shielding the thickness for plutonium is complicated by the many different energies represented in the gamma radiation emitted during decay of the plutonium isotopes. Dose rate predictions are also frequently confused by gamma from varying content of fission product impurities in the plutonium, as well as other gamma radiation induced through alpha and neutron particle absorption within the source material or its environment. After assumptions are made for these many factors the radiation data for shielding determination is still frequently inadequate because of wide variations in dose rates resulting from self-absorption. The degree if self-shielding is in turn dependent on nature of the plutonium compound, degree of compactness, weight, and over-all geometrical distribution of the source material. By preparing a variety of plutonium samples representing combinations of these varying factors, actual dose rates and gamma spectra, as obtained from them, can then be extrapolated for application to specific situations.
Date:
October 22, 1959
Creator:
Moulthrop, H. A.
System:
The UNT Digital Library
4-X program: UO{sub 3} plant expansion
None
Date:
September 16, 1954
Creator:
Ingalls, W. P.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
6.70 EV Resonance in U²³⁸
"Using the Brookhaven fast chopper, transmission curves were obtained for the 6.70 +/- .06 ev resonance in U238 using four different thicknesses of natural uranium metal." The measurements for the transmission curves are summarized in the table provided.
Date:
November 9, 1953
Creator:
Levin, Jules S.
System:
The UNT Digital Library
An 8-Foot Axisymmetrical Fixed Nozzle for Subsonic Mach Numbers Up to 0.99 and for a Supersonic Mach Number of 1.2
From Introduction: "This paper, which should be of interest to those concerned with transonic wind tunnels, covers the design and operating characteristics of the nozzle."
Date:
February 23, 1950
Creator:
Ritchie, Virgil S.; Wright, Ray H. & Tulin, Marshall P.
System:
The UNT Digital Library
9-Zoom : A One-Dimensional, Multigroup, Neutron Diffusion Theory Reactor Code for the IBM 709
The following document describes the usage and purpose of the neutron diffusion theory reactor program 9-Zoom, a memory-contained program that takes advantage of 709 features such as, for example, preferential order of multiply by zero, and for small problems approaches input-output limitations with excellent convergence properties.
Date:
August 25, 1959
Creator:
Stone, S. P.; Collins, E. T. & Lenihan, S. R.
System:
The UNT Digital Library
10-Megawatt Aqueous Homogeneous Circulating Solution Reactor for Producing Electrical Power in Remote Locations
This Report Presents the Preliminary design of a 10-megawatt powerplant utilizing a circulating fuel type homogenous reactor as a primary heat source.
Date:
August 1, 1953
Creator:
Montgomery, D. W.; Dodson, W. J.; Kaiser, F. F.; Luckow, W. K. & Pashos, T. J.
System:
The UNT Digital Library
10 MWe Sodium Deuterium Reactor Design Report
From foreword: This report describes the goal of the overall SDR program to demonstrate the commercial generation of electrical power using a sodium-cooled reactor.
Date:
1959
Creator:
Davis, Peter J.
System:
The UNT Digital Library
11,400 KW Nuclear Power Plant Employing an Organic Moderated Reactor: Preliminary Description
Abstract: The preliminary design is described for a small electric-power-generating plant powered by an organic moderated reactor. System and component requirements are discussed and possible design configurations and equipment are described.
Date:
1957
Creator:
Wheelock, C. W.
System:
The UNT Digital Library
15 MW Gas-Cooled Closed-Cycle Reactor Power System Study: Final Report, Volumes 1-2
This report covers a feasibility study for a 15 megawatt gas cooled reactor power system, conducted by the Ford Instrument Company Division of the Sperry Rand Corporation during the months of March to August 1956.
Date:
April 1, 1957
Creator:
Ford Instrument Company
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.
System:
The UNT Digital Library
20,000 KW Nuclear Power Plant Study for United States Atomic Energy Commission
Introduction: In September of 156, Gilbert Associates, Inc., entered into a contract with the United States of America, acting through the United States Atomic Energy Commission, for the study and preliminary design of a nuclear power plant being considered for integration into a central station power system at an overseas site.
Date:
July 7, 1957
Creator:
Gilbert Associates, Inc.
System:
The UNT Digital Library
20-MW D₂O-Moderated Experimental Boiling Water Reactor Design Studies
None
Date:
February 1957
Creator:
Iskenderian, H. P.
System:
The UNT Digital Library
25 content of initial lots of Hanford UO{sub 3}
At the time the first UO{sub 3} from so-called ``full-level`` Redox runs was shipped from 224U, the % U{sub 235} as determined in 222-S appeared high when compared with theoretical values from the burn-out curve. Close agreement between the 222-S results and % U{sub 235} determined by K-25 on lots 007, 008, and 009, however, indicated that a considerable heel of cold uranium in Redox had been blended with the first ``full level`` material. This explanation has been verified by data collected over the past weeks and provided this report. It has also been verified by the % U{sub 235} found in lots later than 010* (after most of cold uranium flushed out of Redox) which ranged from 0.66% to 0.64%.
Date:
May 28, 1952
Creator:
Work, J. B.
System:
The UNT Digital Library
"25" Critically Consultation with J. W. Morfitt : April 3, 1950
Summary: "Criticality was considered impossible in any contingency encountered in practice under either of the following conditions which include no safety factor: (a) In any isolated cylinder not more than 5 in. in disruptor, if the total amount of U235 present does not exceed 7.5 Eg. (b) In an isolated vessel of any shape and size, if the total amount of U235 present does not exceed 880 g. An "isolated" vessel is one which does not "see" more than 0.1 [...] other vessels containing fissionable material."
Date:
April 3, 1950
Creator:
Merrill, E. T. & Sege, G.
System:
The UNT Digital Library
25 Process Assistance for Period of March 21, 1955 to April 1, 1955
None
Date:
April 11, 1955
Creator:
Culler, F. L.
System:
The UNT Digital Library
25 Process Assistance. For Period of May 2, 1955 to May 13, 1955
None
Date:
May 23, 1955
Creator:
Culler, F L
System:
The UNT Digital Library
A 37,500 KW Power Reactor with Competitive Possibilities
The following report follows the study on economics of nuclear power generation using a light water reactor.
Date:
February 26, 1954
Creator:
Thompson, W. I. & Cohen, Karl
System:
The UNT Digital Library
50-Channel Pulse-Height Analyzer Accelerator Type. Maintenance Manual
None
Date:
December 15, 1953
Creator:
Heller, R. E.
System:
The UNT Digital Library
AN 80 MEGAWATT AQUEOUS HOMOGENEOUS BURNER REACTOR. Reactor Design and Feasibility Problem
An 80 Mw aqueous homogeneous burner reactor suitable for producing 20 Mw of electricity at a remote location is described. The reactor fuel consists of a light water uranyl sulfate solution which acts as its own moderator and coolant. The uranium is highly enriched (93% U/sup 235/). The primary considerstions for the design were simplicity and reliability of the components, automatic demand control and safe for any load change, full xenon override not required, possibility of construction within the immediate future, and economic operation not the cortrolling factor. Reasonably complete studies are presented for the reactor physics, safety, stability, chemistry, hent transfer, and operation of the system. (auth)
Date:
August 1, 1957
Creator:
Chapman, R.H.; Collins, H.L.; Dollard, W.J.; Fieno, D.; Hernandez- Fragoso, J.; Miller, J.W. et al.
System:
The UNT Digital Library
100 Area process improvement program for the period November 1954--April 1955
This is the second of a series of documents issued quarterly. The documents present, for critical examination by management and for the information of related groups, that portion of the future 100 Area technical program which relates directly and more or less immediately to the Technical-Manufacturing efforts to increase both power levels and production. An attempt is made to describe and justify the key production tests planned for the following six month period. Only those tests necessary for the relief of technical and process limitations and vital to the slug improvement program are included. Best estimates of changes in current Process Specifications during the ensuing six months are also given. To further longer range planning, power level forecasts based on foreseeable changes of technical limits and scheduled physical changes of the water plants and reactors are extended several years into the future.
Date:
November 19, 1954
Creator:
Reinker, P. H. & Bupp, L. P.
System:
The UNT Digital Library
100 Area Process Water Pressure Decay Test Program: Part 1
The increase in process tube outlet water temperature to 90{degree}C resulted in increased emergency water flow requirements as indicated by recently approved curves which establish minimum crossheader pressure requirements for the first three minutes following an electrical power failure. To determine whether 190 Building secondary process water pump capacities are adequate for current minimum reactor water pressure requirements, process water pump trip-cut tests are being conducted at all reactors by the Process Unit in accordance with recommendations of the Reactor Process Committee. The results obtained to data in these tests, as well as current plans for the remaining tests, are presented in this document.
Date:
January 2, 1953
Creator:
Thompson, P.
System:
The UNT Digital Library