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FUEL ELEMENT DEVELOPMENT PROGRAM FOR THE PEBBLE BED REACTOR. PHASE I. Progress Report for May 1, 1959 to October 31, 1959

Description: 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… more
Date: November 30, 1959
Partner: UNT Libraries Government Documents Department
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MODEL STUDIES OF FLOW AND MIXING IN THE PARTIALLY ENRICHED GAS-COOLED POWER REACTOR

Description: 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 wer… more
Date: November 30, 1959
Creator: Flanigan, L.J.; Whitacre, G.R. & Hazard, H.R.
Partner: UNT Libraries Government Documents Department
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SM-2 Critical Experiments : CE-1

Description: 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, … more
Date: November 30, 1959
Creator: Noaks, J. W.; McCool, W. J.; Robinson, R. A.; Schrader, E. W. & Weiss, S. H.
Partner: UNT Libraries Government Documents Department
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SRE Fuel Element Damage: An Interim Report

Description: 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.
Partner: UNT Libraries Government Documents Department
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SRE FUEL ELEMENT DAMAGE. Interim Report

Description: 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. O… more
Date: November 30, 1959
Creator: Jarett, A.A. ed.
Partner: UNT Libraries Government Documents Department
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The Thermal Expansion of Synthetic Graphites at Temperature Intervals Between 80 and 2000f

Description: 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 wi… more
Date: November 30, 1959
Creator: Allen, R. D.
Partner: UNT Libraries Government Documents Department
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Variable Moderator Reactor Development Program. Quarterly Progress Report No. 2

Description: 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 co… more
Date: November 30, 1959
Partner: UNT Libraries Government Documents Department
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DIFFUSION OF PLASMA PARTICLES ACROSS A MAGNETIC FIELD

Description: 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.
Partner: UNT Libraries Government Documents Department
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ELECTROLYTIC DISINTEGRATION OF ZIRCALOY-2 IN NITRIC ACID SOLUTIONS

Description: 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 dec… more
Date: November 27, 1959
Creator: Clark, W. E. & Peterson, S.
Partner: UNT Libraries Government Documents Department
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MICRO-ELECTROPHORETIC DETERMINATION OF THE ZETA POTENTIAL OF THORIUM OXIDE

Description: 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.
Partner: UNT Libraries Government Documents Department
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ML-1-1A CORE STUDIES WITH THE GCRE CRITICAL ASSEMBLY

Description: 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 se… more
Date: November 27, 1959
Creator: Egen, Richard A.; Hogan, William S.; Dingee, David A. & Chastain, Joel W.
Partner: UNT Libraries Government Documents Department
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Radioactivity in the Environs of the Savannah River Plant, January to July 1954

Description: 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.
Partner: UNT Libraries Government Documents Department
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The Determination of Excessive Emulsification by Coalescence Behavior Measurements

Description: 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 te… more
Date: November 25, 1959
Creator: Parrett, O. W.
Partner: UNT Libraries Government Documents Department
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Expansion program 190 Building studies results

Description: 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 condi… more
Date: November 25, 1959
Creator: Quackenbush, C. F.
Partner: UNT Libraries Government Documents Department
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Experimental evidence to support the double head wave method of generating a rare faction first motion

Description: 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… more
Date: November 25, 1959
Creator: Werth, G. C.
Partner: UNT Libraries Government Documents Department
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Recovery of Uranium and Plutonium From Sulfuric Acid Decladding Solutions

Description: 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. R… more
Date: November 25, 1959
Creator: Horner, D. E. & Coleman, C. F.
Partner: UNT Libraries Government Documents Department
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Solvent Extraction Recovery of Vanadium (and Uranium) From Acid Liquors With Di(2-Ethylhexyl) Phosphoric Acid

Description: 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 chemi… more
Date: November 25, 1959
Creator: Crouse, D.J. & Brown, K.B.
Partner: UNT Libraries Government Documents Department
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On reducing the amplitude of surface waves by source arrays

Description: The Geneva conference of experts stated that surface waves help define the nature of a seismic perturbation. A `phase equalization` method has been proposed by several seismologists to determine the polarity of the source using crustal surface waves. In this report a horizontal source array is designed which will reduce the amplitude of the crustal surface waves by a factor of five. Experimental data from Geophysical Prospecting is cited to support the effectiveness of such arrays. It is though… more
Date: November 23, 1959
Creator: Werth, G. C.
Partner: UNT Libraries Government Documents Department
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Palm content of production metal

Description: Purpose of this study was to determine the {sup 237}Np input to the Purex process. The {sup 237}Np content of 639 g Pu/ton U irradiated fuel was found to be 1.78 {plus_minus} .09 g/ton of uranium at the 95% confidence level. Standard recovery for the chemical method was 96.7%, 98.0% for the sampling.
Date: November 23, 1959
Creator: Campbell, M. H. & Swift, W. H.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report for October 1959

Description: Pu output from separations plant was less than scheduled, but year-to- date production exceeded commitment by 4%. The Palm recovery run in Purex was the most successful to date. UO{sub 3} production and shipments met schedule. Purex had two pump failures. When Purex 1WW was centrifuged and treated to recover Ce, most of it remained in the centrifugate; only 14% was recovered. The prototype Pu ozonator in Redox performed well. Test runs on an acid precycle flowsheet and a proposed internal recyc… more
Date: November 20, 1959
Partner: UNT Libraries Government Documents Department
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Diffusion of Xenon in Columbium

Description: The diffusion coefficient was calculated for the diffusion of Xe through Nb and found to be 0.064 exp (-18,600/RT).
Date: November 20, 1959
Creator: Gregory, D. P. (Derek P.) & Leavenworth, H. W. (Howard W.)
Partner: UNT Libraries Government Documents Department
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