Resource Type
Serial/Series Title
NACA Research Memorandums
181
Atomic Energy Commission Reports
99
Hanford Works Reports
42
NACA Technical Reports
37
HW (Series)
32
University of California Radiation Laboratory Reports
17
Oak Ridge National Laboratory Reports
16
Report (U.S. Atomic Energy Commission)
15
GJBX
13
Battelle Memorial Institute Reports
10
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Pole-Face Windings
"A summary is presented of a preliminary study of the application of pole- face windings to the Cambridge Electron Accelerator. Estimates are made of the currents required, the forces on the wibdings and the voltages induced by the magnetic flux. The possibility of automatic control of the pole-face currents in explored, and feasible control systems are suggested."
Date:
June 20, 1957
Creator:
Rees, John
Object Type:
Report
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
Object Type:
Report
System:
The UNT Digital Library
Drying of Charcoal Used for Adsorption of Gaseous Fission Products from Homogeneous Reactors
In homogeneous nuclear reactors significant quantities of radioactive inert gaseous fission products must be separated from the fuel solution for disposal. The present disposal scheme, which is employed on the HRT, is to pass the mixture of fission product gases and oxygen through a charcoal adsorption bed. the oxygen passes through the bed relatively un-adsorbed, but the radioactive inert gases are adsorbed and are displaced from the bed bed very slowly giving the gases a much greater residence time than would exist if no bed were used. This long residence or "holdup" time permits the short-lived inert gases to decay away before emission to the atmosphere and thus greatly reduces the safety hazard produced by disposal of the gases to the atmosphere. The same effect could be obtained by using a large holdup tank, but the charcoal bed is much more compact and thus required less shielding.
Date:
December 20, 1957
Creator:
Funderburg, J. M. & Moss, L. I.
Object Type:
Report
System:
The UNT Digital Library
Formulas Pertaining to Weak-Shocks
Certain solutions of the cylindrical wave-equation, such as the Possio integral, which are needed in the investigation of 2-dimensional weak-shocks are are determined in this paper.
Date:
December 20, 1954
Creator:
Owens, O. O.
Object Type:
Report
System:
The UNT Digital Library
Flotation Characteristics of Florida Phosphate Leached-Zone Material, Progress Report No . 7
Although the results reported herein are rather encouraging and show the possibilities of utilizing flotation to increase recoveries and in some instances grades, they should not not be considered an optimum. As stated previously, time did not permit a detailed investigation of all reagents an conditions to obtain maximum grades and recoveries, but sufficient data, with enough typical samples, have been obtained to indicate a definite trend and encouragement for further studies. A comparison of the flotation results obtained with each of the samples is presented in Table 2.
Date:
December 20, 1955
Creator:
Snow, Robert E. (Robert Ellis)
Object Type:
Report
System:
The UNT Digital Library
Thermal-Neutron Flux at the HRE-2 Core Wall, Determined from Zircaloy-2 Induced-Activity Measurements During Runs 13, 14, 16, 17, 18, 19, 20 and 21.
The thermal-neutron flux prevailing near the upper hole in the HRE-2 core wall was determined from measurements of the induced activity in a specimen cut from the edge of the hole. The specimen was removed following run 21 and was thus exposed to reactor neutrons during runs 13, 14, 16,17, 18. 19, 20, and 21. The neutron flux, calculated for an average core power level of 2 Mw, was 2.8 x10^13 neutrons/cm^2 sec. the core wall area from which the specimen was removed was located approximately 16-in. from the core center.
Date:
December 20, 1960
Creator:
Baker, J. E.
Object Type:
Report
System:
The UNT Digital Library
Instruction Manual, Mercury Relay Pulse Generator Model 1-1212C
The Model Q-1212C Pulser is a single frequency (60 pps) generator whose output waveform is characterized by a rise-time of less than 4 mµsec and, depending upon the method of termination, an exponential decay having a time constant of 300 or 600µsec. The waveform approximates that produced by a radiation detector. The waveform approximates that produced by a radiation detector. The maximum available output from the instrument is 10 volts, positive or negative polarity, and is continuously adjustable by means of step switches and a 10-turn potentiometer. The potentiometer has a linearity of 0.1%.
Date:
September 20, 1960
Creator:
Fairstein, E.
Object Type:
Report
System:
The UNT Digital Library
Nuclear and Radiation Hazards Evaluation of SRE Fuel Processing and Storage
Nuclear and radiation hazards have been investigated for all phases of operation to be carried out in the mechanical decladding of SRE fuel elements. The SRE fuel is 2.8% enriched with a maximum burnup of 1,000 Mvd/ton and minimum cooling of 120 days. Each element contains 9 kg of uranium metal (~2 kg U-235) and is made up from 84 slugs (3/4"D x 6'"), clad with (10 mil wall) stainless steel tubing. It is planned to ship the fuel from Santa Susana, California, to Oak Ridge in the modified PAR loop carriers, with a maximum of 10 elements being shipped in each carrier per trip.
Date:
May 20, 1959
Creator:
Suddath, J. C.
Object Type:
Report
System:
The UNT Digital Library
The Laplace Transform Method of Obtaining X-ray Spectral Energy Distributions
This method essentially consists of analyzing x-ray filtration data in terms of Laplace transforms and obtaining the spectral energy distribution in terms of a sum of the corresponding inverse Laplace transforms. Some of the functions which are especially suited for this application are given and a graphical method of analyzing filtration data in terms of these functions is described. Examples of the practical application of this method to several low energy x-ray machines are included with a discussion of the advantages, disadvantages, and probable uncertainties which are involved.
Date:
November 20, 1954
Creator:
Emigh, C. Robert
Object Type:
Report
System:
The UNT Digital Library
Hedstrom Plot for the Calculation of Laminar Flow Pressure Drop for the Bingham Plastic Materials with Hedstrom Numbers from 0 to 10(15)
The results of a machine calculation of a modified Fanning-friction-factor Hedstrom plot for Hedstrom numbers from 0 to 10(10) are presented in graphical and tabular form.
Date:
June 20, 1957
Creator:
Thomas, D. G.
Object Type:
Report
System:
The UNT Digital Library
Fused Salt Compositions
The compositions of the compounds and fused salt mixtures referred to in the ANP project by numbers are given.
Date:
June 20, 1957
Creator:
Barton, C. J.
Object Type:
Report
System:
The UNT Digital Library
Capillary Flowmeter
The HRT leak detector system consists of four headers each of which are connected on one side to a common supply of pressurized water and on the other side by individual tubing to the ring grooves of approximately twenty flanges. There are two methods of detecting the loss of water that are particularly applicable to the HRT: (1) By the loss of pressure in a constant volume system; (2) By the measurement of flow from a constant pressure system. It was determined to investigate the second method which requires a flowmeter capable of measuring flows of .5 cc or less of water per hour. The experiment flowmeter constructed performed almost exactly as the design calculations predicted.
Date:
February 20, 1957
Creator:
Hise, E. C.
Object Type:
Report
System:
The UNT Digital Library
Stress Corrosion in the HRT Mockup
Stress corrosion was found in 8 components of the HRT mockup; only of four of these actually shut down the loop. All of the failures have occurred in the high-pressure system of the loop.
Date:
May 20, 1957
Creator:
Harley, P. H.
Object Type:
Report
System:
The UNT Digital Library
The Rhode Island and Providence Plantations Atomic Energy Commission Nuclear Science Center Volume II - Safeguard Report
This report presents the description and safeguard evaluation of an open pool research and test reactor rated at one megawatt. The reactor is being proposed by the General Electric Company to the Rhode Island and Providence Plantation Atomic Energy Commission.
Date:
May 20, 1959
Creator:
General Electric Company
Object Type:
Report
System:
The UNT Digital Library
Neutron and Gamma Flux Attenuation in a Withdrawn SRE Control Rod
An investigation was made of the neutron and gamma flux distribution along the entire length of a withdrawn control rod in the SRE in order to determine heating, activation and dose rates produced by the streaming neutrons and gammas.
Date:
March 20, 1959
Creator:
Horst, K. M. & Aline, P. G.
Object Type:
Report
System:
The UNT Digital Library
Final Summary Safeguards Report For The General Electric Test Reactor
This report is submitted to the U. S. Atomic Energy Commission as a final summary safeguards and hazards evaluation of a proposed test reactor at its Vallecitos Atomic Laboratory in Alameda County of California. It is the purpose of this report to provide sufficient data to obtain an AEC facility license for the reactor.
Date:
February 20, 1958
Creator:
Andersen, R. K. & Jacobs, I. M.
Object Type:
Report
System:
The UNT Digital Library
Magnetic Field Distributions in a Pinched Discharge
By use of small magnetic probes inserted into the discharge, the magnetic field distributions in the interior of a high-power pinched discharge have been measured as a function of time. From these data the current distributions can be deduced. By applying a static pressure calculation, in the cases when the radical pinch accelerations are small, the plasma pressure nkT in the pinch has been determined, with superimposed axial magnetic fields, and for stable and unstable configurations.
Date:
November 20, 1956
Creator:
Burkhardt, L. C.; Lovberg, Ralph H. (Ralph Harvey) & Phillips, J. A.
Object Type:
Report
System:
The UNT Digital Library
Biology Division Semiannual Progress Report for Period Ending February 15, 1956
Progress report of the Oak Ridge National Laboratory Biology Division providing updates on various projects, experiments, and other work. This report includes a summary of scholarly output from the division and departmental activities in cytology and genetics, mammalian genetics and development, microbial protection and recovery, mammalian recovery, pathology and physiology, general physiology, biochemistry, enzymology and photosynthesis, microbiology, plant biochemistry, and biophysics.
Date:
April 20, 1956
Creator:
Hollaender, Alexander & Carson, Stanley F.
Object Type:
Report
System:
The UNT Digital Library
Chemistry Division Semiannual Progress Report for Period Ending June 20, 1955
Continued work on the adsorbability of metal complexes from concentrated LiCl solutions and LiCl-HCl mixtures on a strong-base anion-exchange resin further demonstrated the much higher adsorbability of these complexes from LiCl solutions than from HCl solutions. The effect is believed to be due to the formation of less strongly adsorbed undissociated chloro-complex acids in the case of the HCl solutions.
Date:
June 20, 1955
Creator:
Taylor, E. H. & Bredig, M. A.
Object Type:
Report
System:
The UNT Digital Library
Aqueous Uranium Slurry Studies
A summary of the laboratory development program on aqueous uranium slurry fuels for the Homogenous Reactor Project during the period April 1951 through March 1953 is presented. These investigations were devoted primarily to a study of the uranium oxides in aqueous suspensions. It was concluded that U(VI) was most likely to be the stable valence state in such slurry fuels and it was shown that β-UO3·H2O platelet crystals were the stable modification at 250°C. Very pure slurries of β-UO3·H2O platelets, uranium concentration of 250g/liter and average particle size of about 10 μ, had favorable settling rates and could be easily redispersed. Their viscosity and corrosion rate in stainless steel were comparable with those in water. Exposure of these slurries to pile radiation disclosed that radiolytic hydrogen and oxygen gas pressure comparable in magnitude to those of uncatalyzed uranyl sulfate solutions could be expected. Fission products in the irradiated slurries were predominantly associated with the solids. Radiation also tended to promote caking of these solids on the walls of the radiation bombs. Uranyl phosphate and the magnesium uranates were briefly investigated as alternate system but were not found satisfactory. The program was discontinued before the feasibility of uranium slurries for reactor …
Date:
October 20, 1955
Creator:
Blomeke, J. O.; Bamberg, J. L.; Blomeke, J. O.; Bruce, F. R.; Fulmer, J. M.; McBride, J. P. et al.
Object Type:
Report
System:
The UNT Digital Library
Chemical Separation of Isotopes Section Semiannual Progress Report For Period Ending December 31, 1954
New systems involving the exchange of boron between boron trifluoride and boron trifluoride addition compounds have been explored. These systems have large separation factors and potentially simple reflux mechanisms. A precise determination of this separation factor for the anisole-boron trifluoride system gave the value (see report). Boron exchange was found to occur between BF and BCl3. Several homogenous catalysts have been found which activate the hydrogen-water exchange, but none are adoptable to the production of deuterium because of the slow exchange rate. Platinum or platinum oxide may be usable as a heterogeneous catalyst with proper support or dispersion techniques. The high-pressure solubility of hydrogen in several amalgams was investigated in connection with a unique countercurrent exchange system. A proposed system involving isotopic exchange between lithium dipivaloylmethane in diethyl ether and lithium hydroxide in aqueous solution was shown to give little or no isotopic separation. Column studies of the carbonate system exchange reaction were concluded with a 40°C run. Slightly higher enrichment of N15 was obtained than at 30°C . The temperature dependence of all in this system was measured between 15 and 45°C. The factor increases with temperature, showing a tendency toward a maximum near 45°C. Isotopic exchange appears to …
Date:
May 20, 1955
Creator:
Clewett, G. H & Drury, J. S.
Object Type:
Report
System:
The UNT Digital Library
Theory of Final State Interactions
Using requirements of analyticity and the unitarity of the S-matrix we obtain the dependence of a transition amplitude on the invariant mass of two particles strongly coupled to other two particle channels. As an example, we consider the production of a Σπ state near the Y*₀ resonance assuming it is coupled to a KN state in an s 1/2 state.
Date:
August 20, 1962
Creator:
Nauenberg, Michael
Object Type:
Report
System:
The UNT Digital Library
L/R Indicator
The evaluation of the inductance of an electrical component is often important in understanding and operating an electrical circuit. Inductance is defined by several equations, the most common being e= -L d1/dt . This equation defines inductance as the constant which relates the back emf produced in an element to the time-rate-of-change of current.
Date:
May 20, 1960
Creator:
Minor, G. C.
Object Type:
Report
System:
The UNT Digital Library
Transistor Pre-Amplifier for Neutron Monitors
In the past several years the use of neutron monitors for Pu concentration monitoring has been expanded in the Chemical Processing Department. Most of these monitors have been quite successful, and considerable effort is being made to improve the operation of both existing and future monitoring systems. One of the major improvements has been the development and use of a transistorized pre-amplifier or impedance matching circuits. This unit solves several problems associated with the use of boron trifluoride (BF3) neutron detectors in process monitoring; e.g., vacuum tube pre-amp failure because heat is not being conducted away.
Date:
April 20, 1960
Creator:
Kelly, P. R.
Object Type:
Report
System:
The UNT Digital Library