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A Useful Solution for Short Cylindrical Shells and Other Applications

Description: The general solution to the basic differential equation d^4w/dy^4 +4w= -4f(y) is transformed from the primary form treated in most texts to an alternate form in which each integration constant corresponds to one edge condition at y=0. The relationships between the integration constants of the two forms are derived and the values for the transformed functions are tabulated. The particular solution is derived in general and given in unique form for various functional forms of f(y). Matrix notatio… more
Date: February 14, 1961
Creator: Moore, S. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fission Product Release from UO2 and by High Temperature Diffusion and Melting in Helium and Air.

Description: The experimental demonstration of fission product release from over heated reactor fuel is necessarily subject in many respects to the arbitrary conditions imposed by the experimenter. Since an almost infinite latitude exists in the choice of materials, atmospheres, gas, velocities, temperatures etc., some allowance for an extrapolation to alternate conditions is definitely in order. The conditions imposed in this study are best described as those most likely to maximize fission product release… more
Date: February 8, 1961
Creator: Parker, G. W.; Creek, G. E. & Martin, W. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preparation of Thorium Oxide from ORNL Thorex Thorium Nitrate

Description: Thorium nitrate, recovered from irradiated thorium metal processed in the ORNL Thorex Pilot Plant, was converted to thorium oxide and then to the fluoride in one pilot-plant-scale and two laboratory-scale runs. Activity distributions, decontamination factors, and safety of the process are treated. (D.L.C.)
Date: February 13, 1957
Creator: McDuffee, W. T. & Yarbro, O. O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Inert Atmospheres in Non-Vacuum Chambers for Welding Applications

Description: In the HRP Welding program, a major part of the welding and fabrication, and some of the testing, is performed using an inert atmosphere. the use of the inert gas consumable arc welding process and dry box welding or other work in a dry box comes within this category. Since much of the work in the project make use of, or requires, inert atmospheres, a general discussion follows of the methods used, description of equipment, processes, quality of atmospheres, purity requirements, kinetics of met… more
Date: February 6, 1957
Creator: Leonard, W. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Calculation of Wall-Scattered Gamma Radiation Escaping through a Shield Opening - Application to the HRT

Description: A simplified method was developed for calculating wall-scatter gamma radiation escaping through a shield opening. The method was applied to the HRT and the results showed that next to the line of sight contribution, scattering of the wall of the shield opening was the main contribution to the dose at the rear edge of the shield. Design charts were prepared that give the dose as a function of the gamma source location with the reactor cell.
Date: February 19, 1957
Creator: Claiborne, H. C. & Fowler, T. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary Estimate of the Cost of Production of 10% Isotopic Purity Oxygen-17 by Chemical Exchange

Description: An order of magnitude estimate was made to determine a minimum cost for 10% pure oxygen-17 when produced by a chemical exchange process. the calculations were based on separations factors of 1.03, 1.01, and 1.003. the cost of product was found to vary from $23 per gram for the large factor to $165 per gram for the smaller.
Date: February 1, 1957
Creator: Klima, B. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Metallographic Examination of ORNL #1, SHE #2

Description: Small Heat Exchanger ORNL #1, type SHE #2, was removed form test stand B after 2071 hours of operation. Thirty-five samples were removed form the entire heat exchanger. The corrosion found on the outside of the tubes exposed to the fluoride mixture ranged to a maximum depth of .004 inches; however, the frequency of occurrence along the tube wall was heavier at the NaK outlet header, which was the hottest area in the heat exchanger. The depth of attack observed on the fluoride side of this heat … more
Date: February 7, 1957
Creator: VanCleve, J. E.; DeVan, J. H. & Crouse, R. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thermal Conductivity of Beryllium : Literature Survey

Description: Lewis in 1929 determined the thermal conductivity of beryllium metal for the first time. The next measurement reported in the open literature on the thermal conductivity of beryllium was by Powell in 1953. Measurements were also made by Grenell, Linebrink, and Johnson at Battelle Memorial Institute in 1947. Their values are in good agreement with those of Powell.
Date: February 12, 1957
Creator: Powers, W. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Extraction of Metal Ions with Di-2-Ethylhexyl Phosphoric Acid

Description: Blake and his co-workers have shown that uranium and other elements can be extracted from acid solutions by various type of organo-phosphorous compounds. Early investigations in the laboratory have demonstrated the applicability of tri-n-alkyl phosphine oxides to the extraction of metal ions from acidic solutions for analytical purposes. This paper is concerned with a similar qualitative investigation of the extraction of metal ions with a di-alkyl phosphoric acid, di-2-ethylhexyl phosphoric ac… more
Date: February 8, 1957
Creator: Ross, W. J. & White, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuel Costs in Batch- and Continually-Processed Homogeneous Reactors

Description: The fuel requirement of a heavy-water moderated, homogenous, power reactor were estimated for a variety of initial loadings, for both bath and continuous methods of fuel removal. This study considered a 12-ft spherical reactor, temperature 250 C, 500 Mw thermal power, 125 Mw electrical power capability, 0.8 load factor, and 4%/year inventory charges for U and D2O. The fuel shipping-and-processing charges were assumed to be $1/gm of fissionable fuel for the "batch" processed reactors, and $0.37/… more
Date: February 8, 1957
Creator: Kasten, Paul R. & Aven, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of Pressure Differentials on Deflection of the Outer Fuel Plates of Brazed APPR Fuel Elements

Description: One of the considerations in designing a flat plate fuel element is the resistance of the fuel plates, especially the outer plates in the fuel plate array, to deflection and permanent deformation as a result of pressure differentials. An investigation was recently initiated wit the objective of obtaining preliminary information on the APPR-type fuel element to determine the effect of pressure differentials on the outer plates in the fuel assembly. The APPR-1 fuel element consists of 18 flat com… more
Date: February 7, 1957
Creator: Erwin, J. H. & Beaver, R. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Control System for HRT Cooling Water

Description: The circuits described herein and shown functionally in Fig. 1 are to be added to the HRT control circuit to provide control and protection for the revised HRT cooling water system. The circuitry will provide protection against excess pressure in the demineralized cooling water loop and cooling water activity, will initiate action to insure containment of activity in event of an explosion and will provide emergency cooling water from the tower basin when required.
Date: February 11, 1957
Creator: Moore, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of HRT Core Sample Holder Upon Core Flow Pattern and Pressure Drop

Description: The measured pressure drop across the reactor core, with the sample holder in place, is 6.9 psi, more than twice the estimated value. Better estimates, based on more rigorous mathematical analysis, should be possible for future problems of this type. The 2% density difference which produced the relatively high velocity of approximately 1 fps, in this experiment, will result from a temperature difference of about 8 C. It is concluded that the bulk fluid temperature near the sample holder will be… more
Date: February 4, 1957
Creator: Hannaford, B. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Bellows Failure in Solids Separation Loop of the HRT Mockup

Description: The failure of the valve bellows would appear to be due to a combination of stress corrosion and crevice corrosion. Stress corrosion occurred as evidenced by the transgranular branched cracking found in the bellows and in the base which which was joined to the bellows. It seems probable that chlorides were present, which, along with the residual stresses present in the bellows assembly, created the necessary conditions for stress corrosion to occur. Crevice corrosion occurred probably due to he… more
Date: February 5, 1957
Creator: Kegler, T. M., Jr. & Hammond, J. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Spectrographic Analysis of Normal Human Tissue from Miami, Florida

Description: All tissues included in this report were received from Miami, Florida and the majority are from Jackson memorial Hospital. They were collected, ashed and analyzed according to the methods described in ORNL-CF-57-2-2. The average value of the concentration for each element in a tissue is the average of the concentrations in only those samples of the tissue which contained the element. For example, if, of 25 lives analyzed, only 10 contained lead, the average for lead in liver is the average of t… more
Date: February 28, 1957
Creator: Tipton, I. H.; Cook, M. J.; Steiner, R. L.; Foland, J. M. & McDaniel, K. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Spectrographic Analysis of Normal Human Tissue from Dallas, Texas

Description: All tissues included in this report were received from Dallas, Texas and were collected, ashed and analyzed according to the methods described in ORNL-CF-57-2-2. The average value of the concentration for each element in a tissue is the average of the concentrations in only those samples of the tissue which contained the element. For example, if, of 25 lives analyzed, only 10 contained lead, the average for lead in liver is the average of those 10 values. For those tissues in which an element d… more
Date: February 26, 1957
Creator: Tipton, I. H.; Cook, M. J.; Steiner, R. L.; Foland, J. M.; McDaniel, K. K. & Fentress, S. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Methods of Collection, Preparation and Spectrographic Analysis of Human Tissues

Description: To determine the maximum permissible concentration (MPC) of a radionuclide which may be ingested or inhaled with exceeding accepted levels of exposure tot he human body, it is necessary to know the average normal concentration of the natural element in the various tissues of the body. Any element may be ingested or inhaled as the element or as a compound. Although nearly all elements have been observed in living tissue, few quantitative observations had been made before 1950. Preliminary studie… more
Date: February 28, 1957
Creator: Tipton, I. H.; Cook, M. J.; Steiner, R. L.; Foland, J. M.; Fentress, S. D. & McDaniel, K. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Instrumentation Flow Plan Symbols and Recommended Drawings : a Standard System for ORNL Instrumentation Applications Work

Description: This report is presented in order to provide a satisfactory system of symbols and identifications for process-instrumentation equipment and to promote a uniformity of practice that will simplify and expedite instrumentation work. It is intended that the systems presented here should be capable of designating and identifying the multitude of instrumentation items which are used for control and operation of conventional processes, as well as for specialized work peculiar to ORNL. Instrument Socie… more
Date: February 21, 1958
Creator: Adams, R. K.; Davis, D. G. & Hyland, R. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Determination of Trivalent Uranium in Fluoride Salt Mixtures by the Modified Hydrogen Evolution Method

Description: The hydrogen evolution method for the determination of uranium trifluoride which was developed by Manning, Miller and Rowan has been used for the determination of trivalent uranium in this laboratory for the past three years. The method has been applied to many different sample types supposedly pure UF3, mixtures of UF3 and UF4 and the large variety of mixtures of fluoride salts that have been investigated as possible nuclear fuels. These mixtures contained alkali metal, beryllium and zirconium… more
Date: February 26, 1956
Creator: White, J. C.; Meyer, A. S., Jr.; Vaughan, W. F.; Ross, W. J. & Manning, D. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of a Cubic Oxide Protective Film on Zirconium

Description: Observations of the effects of neutron damage to zirconium oxides led to the conclusion that the cubic form of ZrO2 is more stable to such damage than the monoclinic form. It has been reported that zirconium corrodes more rapidly in certain liquids when exposure is made under radiation (neutrons and fission products). It is well known that on heating monoclinic ZrO2 a transformation, monoclinic to tetragonal (very similar to cubic), occurs at about 1500°C. The transformation involves sufficient… more
Date: February 21, 1956
Creator: Johnson, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Technology of Uranium Dioxide a Reactor Material

Description: Consideration has been given to various forms of fissionable material for use in atomic reactors, including the pure metals, their alloys and compounds. Of particular interest is the dioxide of uranium which is refractory and corrosion resistant in some environments.The oxide is useful in both granular and bulk forms. Small grains of uranium oxide can be mixed with other materials to form matrix type elements where they serve either as a convenient or necessary form of fuel or fertile material.… more
Date: February 21, 1956
Creator: Johnson, J. R.; Doney, L. M.; Fulkerson, S. D.; Taylor, A. J.; Warde, J. M. & White, G. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Separation of Isotopes Section Semiannual Progress Report for Period Ending June 30, 1955

Description: The countercurrent gas-liquid system BF3(g)—anisole·BF3(l) for the concentration of boron isotopes has been studied. The single-storage separation factor varies from 1.039 at 0°C to 1.029 at 30°C. Rate of exchange is rapid, and, with efficient contacting equipment, complete exchange may be obtained in less than 15 sec. A total separation of 1.525 has been realized in laboratory equipment. The critical-product reflux reaction is quite efficient. Only about 55 moles of BF3 remain in each million … more
Date: February 23, 1956
Creator: Clewett, G. H. & Drury, J. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Enthalpies and Heat Capacities of Solid and Molten Fluoride Mixtures

Description: The enthalpies and heat capacities of seventeen fluoride mixtures in the liquid state have been determined using Bunsen Ice Calorimeters and copper block calorimeters. The fluoride mixtures were composed of the fluorides of two or more of the following metals: lithium, sodium, potassium, beryllium, zirconium, and uranium. The enthalpies and heat capacities of most of these mixtures were studied in the solid state also. Estimates of the heat of fusion have been made. General empirical equations … more
Date: February 1, 1956
Creator: Powers, W. D. & Blalock, G. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Monte Carlo Estimation of the High Energy Neutron Flux Distribution in the ORNL Graphite Reactor

Description: The flux through a given region is proportional to the total lengths of the neutron flight paths that intersect that region. The analytical Monte Carlo procedure manufactured neutron flight paths and totaled the lengths of all paths intercepted by the regions illustrated in Figure 1. The procedure was designed to utilize the various symmetries in the lattice. / Consider a portion of the lattice whose planar cross-section is shown in Figure 5. If R is the region in which the flux is to be estima… more
Date: February 23, 1955
Creator: Moshman, Jack
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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