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Nuclear Battery-Thermocouple Type Summary Report

Description: The potential usefulness of approximately 1300 radioactive isotopes as a heat source for the thermoelectric generator was investigated. Only 47 were found to have the proper characteristics of high specific activity and usable haif-life combined with an easily absorbable radiation. These isotopes are discussed showing possible sources of supply, the hazards involved, and the expected performance. Three large Po/sup 210/ heat sources were designed and constructed (for battery use), including one… more
Date: October 1, 1960
Creator: Blanke, B. C.; Birden, J. H.; Jordan, K. C. & Murphy, E. L.
Partner: UNT Libraries Government Documents Department
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Mass Transfer Coefficients and Interfacial Area in a One Stage Pulse Column

Description: Over-all mass transfer coefficients were determined independently of the interfacial area by considering the operation of the pulse column to be a stage- wise process. The calculated coefficients describe only the operation of the pulse column for the free rise of organic droplets through a stage, since in the downstroke the aqueous phase passes through the organic phase in the form of rivulets preferentially wetting the plates. The driving force for transfer was based on the aqueous phase conc… more
Date: November 1, 1960
Creator: Konopik, A. E. & Burkhart, L.
Partner: UNT Libraries Government Documents Department
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Determination of Aerodynamic Drag Parameters of Small Irregular Objects by Means of Drop Tests

Description: Drag coefficients were determined for various irregular objects such as glass fragments, stones, steel fragments, and spheres by means of drop tests for use in a mathematical model to correlate nuclear explosion blast experiments. Drop tests were also made on small laboratory animals and extrapolated to estimate the drag properties of man. A method was developed to estimate the average drag properties of man from his total surface area. (D.L.C.)
Date: June 1, 1960
Creator: Fletcher, E. R.; Albright, R. W.; Goldizen, V. C. & Bowen, I. G.
Partner: UNT Libraries Government Documents Department
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Methods and Techniques of Fallout Studies Using a Particulate Simulant

Description: The fallout hazard and protection factors in current use for large groups of buildings, i.e., urban residential areas, business districts, industrial complexes, government centers, Atomic Energy Commission facilities, and academic and medical institutions, are largely unsubstantiated by experimental evidence. These data are important for personnel protection on a national basis in the event of war and on a local basis in the event of certain types of nuclear accidents. The need for such informa… more
Date: August 1, 1960
Creator: Lee, W. & Borella, H.M.
Partner: UNT Libraries Government Documents Department
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Zero Field Magnetic Properties of Gadolinium Terbium, and Samarium

Description: The mutual inductance or apparent susceptibility due to the presence of the sample in a coaxial inductance coil was observed for Gd, Tb, and Sm in fields of a few gauss over the respective temperature ranges of 78 to 310 deg K, 78 to 235 deg K, and 4.2 to 150 deg K. A paramagnetic Curie point of 284.2 deg K was found for Gd. For Tb, a transition was found which occurred to within 1 deg of the predicted temperature of 220 deg K, and a second peak occurred at 229.4 deg K which is within 2 deg of … more
Date: November 1, 1960
Creator: Hill, E. D. & Spedding, F. H.
Partner: UNT Libraries Government Documents Department
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Thermal Expansion and Phase Inversion of Rare-Earth Oxides

Description: Thermal expansion and phase inversion measurements are reported on oxides of Sc, Y, La, and 12 lanthanide series elements up to 1350 deg C. (J.R.D.)
Date: October 1, 1960
Creator: Stecura, S. & Campbell, W.J.
Partner: UNT Libraries Government Documents Department
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Research and Development of Metal Hydrides. Summary Report for October 1, 1958-September 30, 1960

Description: A detailed study of the fundamental relations in the zirconium -- hydrogen system was made in order to clarify the many points of dispute and to evolve a complete picture describing all phases of this system. An engineering evaluation was made of means for utillzing the various high cross-section metal hydrides in shielding or control applications. These materials would combine the processes of thermalization and absorption. Consequently, they are of considerable interest for use in shielding o… more
Date: November 1, 1960
Creator: Beck, R. L.
Partner: UNT Libraries Government Documents Department
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Equilibrium of the System Lanthanum Nitrate-Praseodymium Nitrate-Nitric Acid-Water-Tributyl Phosphate

Description: A study of the extraction characteristics of the three systems lanthanum nitrate--nitric acid--water--tributyl phosphate, praseodymium nitrate--nitric acid--water--tributyl phosphate, and lanthanum nitrate--praseodymium nitrate nitric acid -water--tributyl phosphate was conducted. The separation factors between praseodymium and lanthanum for the system lanthanum nitrate--praseodymium nitrate-nitric acid--water--tributyl phosphate were shown to be a function of the total nitrate concentration of… more
Date: November 1, 1960
Creator: Sharp, B. M. & Smutz, M.
Partner: UNT Libraries Government Documents Department
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A METHOD OF EFFECTIVELY WIDENING THE BRAGG PEAK IN DEPTH IN THE PATH OF CHARGED HEAVY PARTICLES IN TISSUE

Description: A device is described for the filtration of charged energetic heavy particles resulting in the production of adjacent or separated Bragg peaks within the range of the particles in tissue. Two or more layers of intense ionization at different depths separated by layers of less ionlzation in tissue can be produced. A cylinder of uniform ionization which cuts off sharply in depth in tissue can also be produced. (auth)
Date: January 1, 1960
Creator: Jansen, C.R.; Baker, C.; Calvo, W.; Rai, K.R. & Lippincott, S.
Partner: UNT Libraries Government Documents Department
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The Salt Cycle Process

Description: The Salt Cycle Process is a nuclear fuel processing approach designed for application in compact facilities located at the reactor sites. Irradiated UO/sub 2/ fuels would be processed through a brief sequence of steps and partially purified UO/sub 2/ or UO/sub 2/--PuO/sub 2/ powders recovered, suitable for refabrication into fuel elements. The major steps of the process are the dissolution of uranium oxides in molten NaCl--KCl eutectic by chlorination to form soluble uranyl chloride and the red… more
Date: August 1, 1960
Creator: Benedict, G.E.; Lyon, W.L.; Mudge, L.K.; Swanson, J.L. & Walling, M.T. Jr.
Partner: UNT Libraries Government Documents Department
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Radiation Hazards Encountered in Arc Melting Thorium

Description: A project to provide information on the hazards associated wlth arc melting of Th is described. A general airsampling analysis was made to determine the separation, concentration, and distribution of Th daughter (decay) products throughout arc melting, machining, and forging processes found in a handling facility. The value of well coordinated health physics program is stressed in connection with potential health hazards and personnel protection. Building, equipment, and exhaust ventilation req… more
Date: November 1, 1960
Creator: Lowery, R. R.
Partner: UNT Libraries Government Documents Department
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TEST OF GERMAN UNDERGROUND PERSONNEL SHELTERS

Description: The predicted behavior of German underground personnel shelters, equipment, and certain instrumentation was investigated. Data obtained will be used for evaluation and improvement of present design criteria. Nine reinforcedconcrete underground shelters, designed by German engineers, were tested at the 170-, 155-, 110-, 78-, 26-, 11.5-, and 7.2-psi overpressure ranges as determined from average blast-line instrumentation measurements. Reinforcing steel, doors, and ventilation equipment were rece… more
Date: July 1, 1960
Creator: Cohen, E. & Bottenhofer, A.
Partner: UNT Libraries Government Documents Department
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Reactor Materials Study. Research and Development of Metal Hydrides. Quarterly Report No. 7 for April 1, 1960 to June 30, 1960

Description: High-temperature x-ray diffraction experiments provided confirming evidence regarding the origin of the metastable gamma phase and of the general features of the zirconiumhydrogen phase system. These experiments also showed that the reaction alpha + delta -- beta (the eutectoid reactlon on heating) proceeds at an extraordinarily slow rate, although the reverse reaction proceeds so rapidly that beta phase cannot be retained to room temperature by quenching. The sluggishness of the eutectoid reac… more
Date: July 1, 1960
Creator: Beck, R. L.
Partner: UNT Libraries Government Documents Department
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Laboratory Investigation of Decontaminating Solutions for Primary Loop Decontamination in the New Production Reactor

Description: An investigation was made of methods for decontaminating the primary loop of the New Production Reactor (NPR). Decontamination factors ranging from fifty to several thousand were obtained with several different combinations of cleaning solutions. In general, fission product activity was removed to a lower residual level than was activated corrosion product activity, and carbon steel was easier to decontaminate than was stainless steel. It was necessary to completely remove the oxide film from t… more
Date: November 1, 1960
Creator: Mendel, J. E.
Partner: UNT Libraries Government Documents Department
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ARMY GAS-COOLED REACTOR SYSTEMS PROGRAM. GCRE-I HAZARDS SUMMARY REPORT. ADDENDUM III

Description: The hazards evaluation was modified to reflect certain changes made to the equipment as a result of operating experience. These changes included: the addition of a startup interlock circuit; the modification of a startup interlock circuit; several minor modifications to the control rod actuators; and the addition of the tube-sheet cooling system. (M.C.G.)
Date: May 1, 1960
Partner: UNT Libraries Government Documents Department
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75,000 KILOWATTS OF ELECTRICITY BY NUCLEAR FISSION AT THE HALLAM NUCLEAR POWER FACILITY

Description: For presentation at ASCE Convention in Reno, Nevada on Thursday, June 23, 1860. A description of the Hallam Nuclear Power Facslity is presented. The history of the project, program participants, site description, component development program, reaetor building, reactor structure, reactor core, sodium systems, instrumentation and control, fuel and component handling, auxsilary sustems, special design features, and advantages of sodium graphite reactor systems are discussed. (M.C.G.)
Date: January 1, 1960
Creator: Gronemeyer, F.C. & Merryman, J.W.
Partner: UNT Libraries Government Documents Department
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THERMAL DESIGN OF THE MGCR CORE

Description: The design information is presented in sections on core thermal performance, fuel elements, moderator, and control rods. (J.R.D.)
Date: August 1, 1960
Creator: Rogers, J.T. & Katz, R.
Partner: UNT Libraries Government Documents Department
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