Resource Type
Collection
Serial/Series Title
NACA Research Memorandums
266
NACA Technical Notes
151
Atomic Energy Commission Reports
130
Personal Papers (MS 80-0002)
54
United States Geological Survey Reports
51
Hanford Works Reports
49
HW (Series)
33
Trace elements investigations report
33
University of California Radiation Laboratory Reports
32
AECU (Series)
28
76 More
States
Decade
Month
Language
1,306 Matching Results
Results open in a new window/tab.
Results:
1 - 24 of
1,306
next
Equations of State for Stream-Water Mixtures and Some Representative Applications Analysis
The majority of two-phase flow problems involving equations of state are solved by use of point-wise utilization steam table values. In this manner, problems involving the use of the various flow equations of continuity, momentum and energy are generally forced into iterative solutions. Considerable effort towards the development of an analytical expression for the state equation seems indicated so as to simplify the analysis of two-phase problems, particularly apparent in the analysis of systems undergoing phase transformation as demonstrated by the significant difference between simple theory and experimental critical flow determinations. The assumption of homogeneous, equilibrium mixture is indicated as a first attack upon the problem.
Date:
November 30, 1959
Creator:
Love, W. J.
System:
The UNT Digital Library
Final Technical Report on Physics Research
Results are summarized on theoretical considerations of the excited states of the Ca isotopes, experimental studies of the level structure of Ca42 and Ca44, studies of the production of circularly polarized bremsstrahlung by beta rays, the Moller scattering spectrometer, and the Moller scattering coincidence experiment.
Date:
November 30, 1959
Creator:
McCullen, J. D.; Kraushaar, J. J.; Woolum, J. C.; Sandifer, C. W.; Kliwer, J. K.; Baker, D. et al.
System:
The UNT Digital Library
FUEL ELEMENT DEVELOPMENT PROGRAM FOR THE PEBBLE BED REACTOR. PHASE I. Progress Report for May 1, 1959 to October 31, 1959
Numerous types of high temperature ceramic fuel elements for the Pebble Bed Reactor are being evaluated. Specimens are 1 1/2 in. diameter uranium graphite spheres with external coatings such as silicon carbide or pyrolytically deposited high density graphite and fuel particle coatings such as alumina. Low fission product leakage rates at high temperatures have been observed for some of these coatings. High-level irradiation has given no visible evidence of radiation damage to either the silicon carbide coating or the coating-graphite bond. (auth)
Date:
November 30, 1959
Creator:
unknown
System:
The UNT Digital Library
Fuels Preparation Department monthly report, October 1959
This document details the activities of the Fuels Preparation Department during the month of October 1959. (FI)
Date:
November 30, 1959
Creator:
unknown
System:
The UNT Digital Library
Leveling of Extraction Tool Crane Rails. Section I. Second Performance. Core I, Seed 1. Test Results DL-S-246, FY-59-323
The purpose of the test was to check the extraction crane rails in the area of the reactor pit for level and parallelism. The west extraction crane rail exceeded the allowed tolerance of 1/32 inch at only one location. The elevation of the north bumper was out of tolerance by 1/64 inch. The east extraction crane rail was consistently lower than the west rail by as much as 8/64 inch. The east rail was parallel with the west rail within allowable tolerances over the length tested except at one location where the transit was located, approximately 41 feet from the north bumper.
Date:
November 30, 1959
Creator:
Pazuchanics, Nicholas
System:
The UNT Digital Library
MODEL STUDIES OF FLOW AND MIXING IN THE PARTIALLY ENRICHED GAS-COOLED POWER REACTOR
A quarter-scale flow model, using air as a working fluid, was used to obtain design data for the PEGCPR program. A design for the core-support cylinder, to provide optimum mixing and core-flow distribution, was developed, following which experimentul studies of core-flow distribution, mixing of flow from the two inlets, flow patterns in plenum spaces, flow patterns in the thermal- shield-coolant passage, and pressure drops throughout the model were carried out. Results obtained in the model were then converted to values applicable to helium flow in the prototype. (auth)
Date:
November 30, 1959
Creator:
Flanigan, L.J.; Whitacre, G.R. & Hazard, H.R.
System:
The UNT Digital Library
Periodic Radiation Survey. Section III. First Performance. Core I, Seed 1. Test Results DL-S-231, T-612394
The purpose of the test was to determine the radiation levels inside the concrete enclosures but outside the reactor plant containers after shutdown following plant power operation. Radiation levels at the survey points in the 1-AC and 10BD Boiler Chambers Enclosures and in the Reactor Container Enclosure indicated that no significant radiation hazards were present approximately 25 minutes after all rods had been inserted. The radiation levels approximately 4 minutes after shutdown at the survey points in the Auxiliary Chamber Enclosure indicated that several points were above background, the highest test level being obtained in contact with the East Auxiliary Chamber container drain pipe.
Date:
November 30, 1959
Creator:
Shramko, John, Jr.
System:
The UNT Digital Library
SM-2 Critical Experiments : CE-1
Abstract: Critical experiment studies were performed, varying the parameters U235, B10 and metal to water ratio, in the SM-2 7 x 7 core configuration with 38 stationary elements and seven control rods of the SM-1 (APPR-1) type. An experimental mock-up of the SM-1 was assembled using the basic SM-2 fuel plates. Excellent agreement between the SM-1 boron loading, determined by chemical analysis, and the SM-1 mock-up boron loading, for equivalent bank positions, was noted. Several SM-2 mock-ups, cold clean and midlife, were assembled and studied with regard to reflector effects, flow divider effects, relative control rod array worths, critical rod configurations, and relative power distributions. The results of these experiments indicate as satisfactory a U235 loading of 36.4 Kg and a B10 loading of 63.4 grams for the SM-2. Attention is drawn to numerous power peaks present in the active core. The open seven control rod array has a slight reactivity advantage over the closed seven array and consequent minor disadvantage with respect to "stuck rod" criteria.
Date:
November 30, 1959
Creator:
Noaks, J. W.; McCool, W. J.; Robinson, R. A.; Schrader, E. W. & Weiss, S. H.
System:
The UNT Digital Library
SRE Fuel Element Damage: An Interim Report
Abstract: During the course of power run 14 on the Sodium Reactor Experiment (SRE) at low power, the temperature difference among various fuel channels was found to be undesirably high. Normal operating practices did not succeed in reducing this temperature difference to acceptable values and on July 26, 1959, the run was terminated.
Date:
November 30, 1959
Creator:
Jarrett, A. A.
System:
The UNT Digital Library
SRE FUEL ELEMENT DAMAGE. Interim Report
During the course of power run 14 on the Sodium Reactor Experiment (SRE) at low power, the temperature difference among various fuel channels was found to be undesirably high Normal operating practices did not succeed in reducing this temperature difference to acceptable values and on July 26, 1959, the run was terminated. A series of fuel element inspections was begun to ascertain the cause of these circumstances, and several fuel elements were discovered to have suffered substantial damage. On July 29, 1959, an Ad Hoc Committee was appointed by Atomics Intennational to assist in the analysis of the existing situation in the reactor and the determination of its origin. During the three-month period since the termination of power run 14, there has been a very active program of investigation. The data accumulated duning the operation of the SRE have been re- examined and evaluated. Metallurgical examination was made of a few samples of the fuel and other components of the reactor where possible. Some chemical analysis was made of the coolant and its contaminants. Radiochemical analyses have been made of the coolant and gaseous activity. Reactivity effects were investigated. Scme experimental programs were initiated to examine mechanisms of damage and …
Date:
November 30, 1959
Creator:
Jarett, A.A. ed.
System:
The UNT Digital Library
The Thermal Expansion of Synthetic Graphites at Temperature Intervals Between 80 and 2000f
The mean linear and cubical coefficients of thermal expansion of eight commercial samples of graphite were determined for temperature intervals between 80 and 2000 deg F. The linear thermal expansion was measured with an automatic recording dilatometer using a rod-shaped specimen 2 in. long and 1/4 in. across. The specimen was heated in an atmosphere of helium. The results were in good agreement with those of Currie, Hamister, and MacPherson. The mean linear coefficient was found to increase with temperature. For the samples studied, the mean linear coefficients from 80 to 2000 deg F were 1.50 to 2.34 x 10/sup -6// deg F parallel and 2.26 to 3.45 x 10/sup -6// deg F perpendicular to the grain and were found to vary linearly with the electrical resistivity measured at 32 deg F. (auth)
Date:
November 30, 1959
Creator:
Allen, R. D.
System:
The UNT Digital Library
Time Variation of Thermodynamic Parameters of a Gas in the Region of a Shock Front : Progress Report III
The original goal of this investigation was to compare the thermodynamic characteristics of the gases in and behind the shock fronts in gases at initial pressures in the millimeter range and to compare these characteristics in the geometries of single and double discharges. The shock fronts were not visible, so it was not possible, at these pressures, to get visual data from the shock front itself. The parameters giving the properties of the gases were faces. Measurements made with an image converter camera (which is still in the development stage) agree well with these made with a photomultiplier tube. Differences are observed between the front velocities in the cases studied. These are of the order of 3 to 15 per cent. Considering the nature of the shot to shot fluctuations in the discharges and the inductance variation between the single and double discharges represent a physical difference. The mathematical treatment which says that two equal strength colliding with a wall behaves, has not been shown to be inadequate by this investigation. It was hoped that a stronger confirmation could be fien to the theory, but the accuracy of the data does not warrant it.
Date:
November 30, 1959
Creator:
Eastmond, E. John (Elbert John), 1915-; Hales, Richard Wayne, 1926-; Hoyt, G. D.; Baird, Ramon C.; Chowdhury, P. N. R. & Strong, William J
System:
The UNT Digital Library
Variable Moderator Reactor Development Program. Quarterly Progress Report No. 2
The hydrodynamics code BOCH was used to obtain the relationship between a large number of variables such as voids, flux, pin spacing, power density, and pressure for VMR lattices. Based upon these relationships, a reference core design was selected for examination, using the integrated physics and hydrodynamics analytical modeis. The analog representations of the VMR core kinetics describing the individual blocks of a model block diagram were completed. A simplified core physics analysis was completed, and design parameters were established. An analysis of these parameters using PUREE' was initiated. The first three energy groups and the thermal group were compared with experimental lattices. Portions of the developed code are being used to analyze the critical experiment design and to investigate the reference core design. The critical experiment facility design is about 60% complete. The preliminary program which has been planned includes consideration of the number, kinds, and schedule of experiments to be performed. Portions of the PUREE' physics analysis are being used to generate information for the hazards repert on the critical experiment. (For preceding period see ATL-A-100.) (J.R.D.)
Date:
November 30, 1959
Creator:
unknown
System:
The UNT Digital Library
DIFFUSION OF PLASMA PARTICLES ACROSS A MAGNETIC FIELD
BS>A previous calculation of the rate of diffusion of like charged particles across a magnetic field is generalized. No "a priori" assumption as to the relative magnitude of certain terms need be made and spatial density gradients are permitted in both directions perpendicular to the field. The final result agrees with that given earlier. (auth)
Date:
November 27, 1959
Creator:
Isihara, A. & Simon, A.
System:
The UNT Digital Library
ELECTROLYTIC DISINTEGRATION OF ZIRCALOY-2 IN NITRIC ACID SOLUTIONS
Zircaloy-2 is anodically converted to scaly ZrO/sub 2/ at 60 deg C in 8 M HNO/sub 3/. About 0.5 mole of acid is consumed per faraday, and after saturation of the electrolyte with nitrogen oxides about 0.3 mole of gas is evolved per faraday. The nitric acid is reduced to hydrogen, NO, and N0/sub 2/, with hydrogen predominating if the cathode is Zircaloy and NO if the cathode is platinum. Corrosion specimens of HRT metals were exposed to the electrolysis conditions. From determinations of the decomposition potential of nitric acid it appears that a metal container for the electrolytic process can be protected from stray-current corrosion by holdlng it at a potential --0.5 volt positive to a platinum cathode operating at a current density of 5 to 10 ma/cm/sup 2/. Practical laboratory experiments tended to confirm this conclusion. (auth)
Date:
November 27, 1959
Creator:
Clark, W. E. & Peterson, S.
System:
The UNT Digital Library
MICRO-ELECTROPHORETIC DETERMINATION OF THE ZETA POTENTIAL OF THORIUM OXIDE
A micro-electrephoresis cell is described, and its application to the determination of the zeta potential of thorium oxide is presented. Samples of thorium oxide from different sources, some of which were subjected to certain physical treatments, are charcterized by the zeta potential obtained in water. The zeta potentials produced in solutions of HCl, H/sub 2/SO/sub 4/, KOH, NaOH, Na/sub 4/P/sub 2/O/sub 7/ and Na /sub 3/PO/sub 4/ are also given
Date:
November 27, 1959
Creator:
Boyd, C. M.; House, H. P. & Menis, O.
System:
The UNT Digital Library
ML-1-1A CORE STUDIES WITH THE GCRE CRITICAL ASSEMBLY
Critical assembly studies were conducted tc provide physics and engineering data to aid in developing the Mobile Low-Power Reactor (ML-1). The ML-1-lA core was critical with 59 elements containing 17,906.71 g of U/sup 235/ and had an excess reactivity of 0.381 x 10/sup -2/ DELTA k/k at a moderator temperature of 24.91 deg C. The ratio of maximum element power to core-averaged power was approximately 1.09. The ratio of maximum to core-averaged thermal flux was approximately 1.10. At an 18-deg separation, the shutdown worth of the cadmium-covered control-blade mock-up was 1.14 x 10/sup -2/ DELTA k/k for a 69 element core. Radial and upper axial reflector-moderator void coefficients were - 0.59 plus or minus 0.07 and -0.36S plus or minus 0.015 x 10/sup -2/ DELTA k/ k.per in., respectively. Two lA production fuel elements were evaluated in the critical assembly core. The results predict that the production elements tested contained roughly the same fuel as the critical assembly element and an additional 772 g of stainless steel equivalent on the average. Radial power and neutron flux distributions were measured in a 19-pin lB fuel element. Fairly uniform distributions were observed. Data to evaluate the thermal utilization of this element were …
Date:
November 27, 1959
Creator:
Egen, Richard A.; Hogan, William S.; Dingee, David A. & Chastain, Joel W.
System:
The UNT Digital Library
Radioactivity in the Environs of the Savannah River Plant, January to July 1954
There were significant increases in radioactivity in the environs of the Savannah River Plant during the period from January 1954 to July 1954. All of these increases were relatively small as compared to the maximum permissible concentration. Although fall-out from Pacific tests was the main contributor to the increased activity, some of the increase was due to normal Plant operations. (W.D.M.)
Date:
November 27, 1959
Creator:
Horton, J. H.
System:
The UNT Digital Library
Decontamination of the KER Rupture Experiment Loop. Test Series B - Tests No. 3. Test Series D-Test No. 1.
The first series of tests in the KER-REP-1 loop proved that a fission product contaminated loop could be decontaminated to a safe level for contact maintenance. Since a good decontamination process was available, there was much that could be improved about this process. Further testing of this process and several variations of other processes have been scheduled. The evaluation of these processes includes specific decontamination factors, process corrosion, and loop activity reduction factors (loop decontamination factors).
Date:
November 25, 1959
Creator:
Weed, R. D.
System:
The UNT Digital Library
The Determination of Excessive Emulsification by Coalescence Behavior Measurements
The development of a remotely operated device for determining the coalescence times of plant process streams suspected of containing surfactants such as silicic compounds and fission product zirconium compounds is described. A general correlation between the coalescence times of pilot plant extraction column aluminum nitrate feeds and 3.25 percent tributyl phosphate extractant streams and the observations of column behavior of these streams is demonstrated. The application of the coalescence test to plant streams is given. (auth)
Date:
November 25, 1959
Creator:
Parrett, O. W.
System:
The UNT Digital Library
Expansion program 190 Building studies results
It is the objective of this study to investigate preliminary expansion program requirements for process water, as supplied by 190 Building equipment; from the point of view of practical pumping, flywheel and pump suction head requirements. These requirements are to be determined at this time in such a form and accuracy as to be useful in refined estimating for budget study purposes. In order to obtain the objectives of this study at this time it has been decided to consider five different conditions of process water flow to a reactor. These conditions are flow to the reactor under summer conditions of operation in gallons per minute with a corresponding top of riser pressure in pounds per square inch: 85,000 gal/min, 580 psi; 100,000 gal/min, 480 psi; 130,000 gal/min, 280 psi; 150,000 gal/min, 280 psi; and 150,000 gal/min, 150 psi.
Date:
November 25, 1959
Creator:
Quackenbush, C. F.
System:
The UNT Digital Library
Experimental evidence to support the double head wave method of generating a rare faction first motion
An earlier report suggested a double headwave method of generating a rarefaction first motion. In this method a geologic situation is selected so that energy that has been critically refracted once above the shot and once below shot arrives first. Since the theory of headwaves gives in the usual stationary phase approximation a ninety degree phase shift for each critical refraction, energy that has been critically refracted twice produces a 180 degree phase shift. Oil well data was presented to show that the necessary geologic situation exists in nature. A question has come up regarding the propagation of long wave lengths (16,000 ft) in the thin bed (3000 ft.) above the shot in the geologic situation cited in the earlier report. At the tine of writing of the report it was realized that the thickness of the bed should be considered in propagating the 3 to 5 wavelengths along the bed. The theoretical problem of propagation in high speed elastic bed has not been solved. The best information available at this time indicates that it might indeed be possible to go out into reef country and experimentally find a location suitable to generate a rarefaction first motion by the double …
Date:
November 25, 1959
Creator:
Werth, G. C.
System:
The UNT Digital Library
Recovery of Uranium and Plutonium From Sulfuric Acid Decladding Solutions
Uranium and plutonium were recovered by liquid-liquid extraction from simulated sulfuric acid stainless steel decladding solution with several extractants. Consecutive extraction of U(IV) and Pu(III) or (IV) by 0.1 to 0 3 M primary amine in hydrocarbon-- alcohol diluent appeared promising, and chemical flowsheets were demonstrated in laboratoryscale continuous countercurrent extraction. Extraction of U(VI) with a dialkylphosphoric acid appeared promising when plutonium recovery is not needed. Recovery is also chemically feasible by extraction of U(VI) and Pu(IV) with an N-benzyl secondary alkyl amine or a trialkylphosphine oxide. The amine extracts are stripped with nitric acid, giving a sulfate-nitrate product solution. The organophosphorus extractants permit elimination of the sulfate but require sodium carbonate for stripping. (auth)
Date:
November 25, 1959
Creator:
Horner, D. E. & Coleman, C. F.
System:
The UNT Digital Library
Solvent Extraction Recovery of Vanadium (and Uranium) From Acid Liquors With Di(2-Ethylhexyl) Phosphoric Acid
Bench-scale studies were made on use of di(2ethylhexyl)-phosphoric acid in an organic diluent (Dapex process) for solvent extraction recovery of vanadium from acid leach liquors. Vanadium may be stripped from the solvent by either acidic or alkaline reagents, the former having been studied in considerably greater detail. A process for single-cycle recovery and separation of uranium and vanadium from sulfate leach liquors was shown to be attractive both from the standpoint of operation and chemical costs. Process schemes for recovery of vanadium from uranium-barren liquors are also described. On the basis of the encouraging laboratory results, pilot scale tests for specific applications are recommended. (auth)
Date:
November 25, 1959
Creator:
Crouse, D.J. & Brown, K.B.
System:
The UNT Digital Library