Resource Type
Partner
Collection
Office of Scientific & Technical Information Technical Reports
1,077
Technical Report Archive and Image Library
729
TRAIL Microcard Collection
491
Harris and Eliza Kempner
9
Texas State Publications
7
National Advisory Committee for Aeronautics Collection
6
Abilene Library Consortium
2
Boy and Girl Scout Annual Reports
2
Congressional Research Service Reports
1
Federal Communications Reports
1
8 More
Serial/Series Title
Atomic Energy Commission Reports
225
Hanford Works Reports
182
HW (Series)
180
Oak Ridge National Laboratory Reports
100
AECU (Series)
82
University of California Radiation Laboratory Reports
61
AEC research and development report
56
United States Geological Survey Reports
44
TID
39
United States Bureau of Mines Reports
27
125 More
Country
States
Year
Month
Language
Results:
1 - 24 of
1,833
next
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
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
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 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
105-N charge-discharge rates
Figures have and can be generated that indicate a higher charge-discharge rate if required before 105-N will be comparable with existing reactors. Also, these figures show an apparent operating cost incentive to increase the charge-discharge rates proposed for 105-N. Although these figures may be true by themselves, other figures developed from the same information and stated on a basis that affords a true comparison, show that the proposed rates for 105-N are compatible with those in existing reactors. However, the accomplishments of existing reactors should be considered as a guide only and not as Criteria since the design basis has already been established for Project CAI-816. An average charge-discharge rate has been proposed for 105-N that is compatible with the two main ground rules of the Project. Namely, the capital cost limitation and the plant factor. This rate of 8 tubes/hr. is one that appears to be reasonable from the charge-discharge design aspects and there is a good possibility that it can be increased with operational experience.
Date:
July 2, 1959
Creator:
Nesbitt, J. F.
System:
The UNT Digital Library
190-C pump capacity
The purpose of this document is to update 190-C pump capacity information previous released in HW-52449{sup 1} and HW-58580{sup 2}. Improvements in motor cooling has resulted in raising the previous 3500 HP limit to 3660 HP{sup 3} thus increasing total pumping capacity.
Date:
June 22, 1959
Creator:
Watson, D. F.
System:
The UNT Digital Library
709 Program for Reduction of Exponential Pile Data
A multi-purpose program for processing exponential data has been prepared for the 709 computer. The main purposes of the program is to compute the material buckling from raw data (given counts, time, and counter information) or from previously calculated Athermal's. It is also possible to compute only CeCh (end and harmonic corrections) for a given B11 or series if B11's no counting data being entered. In every case, pile measurements must be submitted as input for corrections.
Date:
August 20, 1959
Creator:
Matsumoto, D. D.
System:
The UNT Digital Library
1024 Channel Time-of-Flight Analyzer for MTR Fast Chopper - Operating Manual
Report on the principle of measuring the time-of-flight of neutrons, magnetic-core storage of detector pulses, how pulses are stored, current generator, storage cycle generator, and cathode ray oscillograph.
Date:
March 11, 1959
Creator:
Petree, F. L.
System:
The UNT Digital Library
1706 KE Water Treatment for Out-of-Reactor Test Facilities.
Water treatment systems for preparing and maintaining high purity water in out-of-reactor or in-reactor test oops are becoming increasingly important. In out0of-reactor experiments the presence of ionic impurities in the water has a marked influence on film formation and corrosion rates. It is therefore , imperative that these impurities be maintained at the lower practical concentration.
Date:
March 30, 1959
Creator:
Demmitt, Thomas F.
System:
The UNT Digital Library
1A Reactor Inlet Hydraulic Valve Position Detector Temperature. Section I. Core I, Seed 1. Test Results DL-S-258-S, RNI-3
The purpose of the test was to determine the internal temperature of the valve position detector for the 1A reactor inlet hydraulic valve with the plant at normal pressure and temperature and at power. The normal operating temperatures for the valve position detector on the 1A reactor inlet hydraulic valve range from a minimum of 287 F to a maximum of 294.7 F.
Date:
November 20, 1959
Creator:
unknown
System:
The UNT Digital Library
Abilene Fire Department Annual Report: 1959
Annual report of the Abilene Fire Department describing the organization and administration, with updates on goals, activities, and accomplishments during fiscal year 1959.
Date:
1959
Creator:
Abilene (Tex.). Fire Department.
System:
The Portal to Texas History
Absolute Measurement of Eta by the Manganese Bath Technique
None
Date:
January 20, 1959
Creator:
deSaussure, G. & Macklin, R. L.
System:
The UNT Digital Library
Absorption of Organic Acids on Thoria
The adsorption of acetic and oleic acids on the surface of thoria was studied by means of infrared spectroscopy. An infrared analysis of the adsorbates before and after adsorption using differential double bean methods indicated that the adsorption of organic acids on thoria surfaces occurs by an esterification reaction between the organic acid and the hydroxylated thoria surface. Ammonia vapor will not adsorb on thoria, indicated the basic character of the hydroxylated surface.
Date:
December 31, 1959
Creator:
Bradford, Harold R. & Wadsworth, Milton E.
System:
The UNT Digital Library
Absorption of Radionuclides Applied to Above Ground Plant Parts : Terminal Report
The attached list of publications is submitted as a year to year and final report of progress on work accomplished under Contract AT(11-1)-159 from 1950 to 1959. Work was initiated on this project in the spring of 1950 and is still in progress as of the date of this report.
Date:
1959
Creator:
Wittwer, S. H. (Sylvan Harold), 1917-2012; Turkey, H. G. & Bukovac, M. J.
System:
The UNT Digital Library
Accuracy of Volume Measurements in a Large Process Vessel
The Non-Production Fuel Reprocessing Program involves the chemical processing of valuable reactor fuels received from privately owned power reactors. It is necessary therefore, to accurately measure the fuel material received in order to insure proper payment to reactor operator and to provide the Atomic Energy Commission with appropriate accountability data. The volume measurement study described herein was conducted in order to determine the limits of accuracy that could be obtained in measuring relatively large volumes of solution under plant processing conditions.
Date:
October 19, 1959
Creator:
Pleasance, C. L.
System:
The UNT Digital Library
Activation Analysis Nuclear Chemical Research Radiochemical Separations. Progress Report No. 8 for November 1958-October 1959
Activities at the Michigan Reactor and pneumatic tube system are outlined. Various modifications including installation and operation of a "bunny" rabbit pneumatic tube system for transferring samples from laboratory to counter are described. Prelimirary investigation for design of a neutron generator for activation work is described. Modifications to the 100-channel pulse-height analyzer including addition of auxillary circuits and additioral detectors are sumnnarized. In nuclear chemistry a cyclotron bombardment to produce long-lived vanadium tracer for yield determinations in activation analysis is described. Summaries of project work which have been published on absolute (d, alpha) reaction cross sections and excitation functions, use of computers in nuclear data analysis, and research on Ir/sup 196/ are presented. Study of the gamma spectra of 33-second Kr/sup 90/, 41-second Xe/sup 139/, and some longer-lived fission product rare gases is reported and a summary of preliminary results is given. Detection of a long-lived isomer of Ag/sup 108/ in old Ag/sup 110m/ samples is reported and new values for the branching ratios of 2.4minute Ag/sup 108/ are given. Activities of the Subcommittee on Radiochemistry are summarized. Development of a radiochemical procedure by the use of amalgam exchange is reported and exchange of the elements Cd, Tl, Zn, Pb, …
Date:
November 1, 1959
Creator:
Maddock, R. S. & Meinke, W. W.
System:
The UNT Digital Library
Adams disassembly procedure for Bldg. 10, Nevada Test Site
The disassembly of the `Adams` primary was scheduled for April 28, 29, and 30, 1959. The method of disassembly is provided as a procedure to be accomplished in order and the time and initials of the person accomplishing each step recorded.
Date:
April 24, 1959
Creator:
Beckman, K. F.
System:
The UNT Digital Library
Addendum to Hazards Summary Report for the Gcre Critical-Assembly Experiments
None
Date:
September 22, 1959
Creator:
Chastain, J. W.; Epstein, H. M.; Hogan, W. S. & Dingee, D. A.
System:
The UNT Digital Library
Adsorption of Xenon in an Activated Charcoal Column
Performance characteristics of two activated charcoal columns at room temperature in separating fission-product xenon from an air stream were investigated by installing each column in the exhaust from an enclosure in which irradiated slugs were dissolved. Breakthrough curves are presented and the variation in xenon concentration within the columns is examined. Theoretical treatments of adsorption columns in the literature are found to agree well with the experimental data. Performance of the colunms is evaluated in terms of concentration factor'' and number of effective theoretical plates. (auth)
Date:
May 11, 1959
Creator:
Cantelow, H. P.
System:
The UNT Digital Library
ADVANCED DESIGNS OF MAGNETIC JACK-TYPE CONTROL ROD DRIVE
The magnetic jack is a device for positioning the control rods In a nuclear reactor, especially in a reactor containing water under pressure. Magnetic actuation precludes the need for shaft seals and eliminates the problems associated with mechanisms operating in water. It consists of a pressure shell, four sets of external stationary magnet coils (hold, grip, lift, pull down), and one Internal moving part (ammature) that impants linear motion to a cluster of rods. (W.L.H.)
Date:
November 1, 1959
Creator:
Young, J.N.
System:
The UNT Digital Library
Advanced Designs of Magnetic Jack-Type Control Rod Drive
Report containing information regarding magnetic jacks, which are devices used "for positioning the control rods in a nuclear reactor, especially in a reactor containing water under pressure" (page 9). Contains a description of the device, its use, test results, and illustrations.
Date:
November 1959
Creator:
Young, Joseph N.
System:
The UNT Digital Library
Advanced Pressurized Water Reactor Study [Part 1]: Phase 1 Report
From preface: This report covers Phase I of the authorized work, consisting of determination of the specific reactor concept and size for the most economic reactor, preparation of a reference design of the most promising concept and estimated capital and generating costs, evaluation of the variations in cost as a function of unit size, and evaluation of the reductions in ultimate costs for a power station having multiple units of the same type.
Date:
July 1959
Creator:
U.S. Atomic Energy Commission. Division of Reactor Development.
System:
The UNT Digital Library
Advanced Pressurized Water Reactor Study [Part 3]: 235 Mw Coal-fired Generating Plant
"This study is one of four initiated in 1958 by the Division of Reactor Development, U.S. Atomic Energy Commission, to assess the feasibility of power generation through the use of certain types of nuclear reactors. These studies are available from the Office of Technical Services, U.S. Department of Commerce, Washington 25, D.C."
Date:
July 1959
Creator:
U.S. Atomic Energy Commission. Division of Reactor Development.
System:
The UNT Digital Library
Advantages of palmolive alternate
It has been proposed that Pu-238 be produced by irradiating neptunium solution in one or more loops in a reactor and then recovering the Pu-238 in a close-coupled separations plant. Such a scheme could replace the more conventional scheme of solid element fabrication, irradiation, and reprocessing for plutonium and neptunium recovery. This document presents the advantages of such a scheme from the standpoint of product purity and Pu-238 production.
Date:
March 17, 1959
Creator:
Coppinger, E. A. & Merrill, E. T.
System:
The UNT Digital Library