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Analytical Method for Inline Plutonium Analyses

Description: Laboratory studies demonstrated the feasibility of a colorimetric method for the in-line analysis of plutonium(III) and plutonium(IV) in the Purex process. Negligible interference was caused by normal variations in the concentration of nitric acid, nitrous acid, or ferric sulfate. (auth)
Date: August 1, 1961
Creator: Overman, R. F.
Partner: UNT Libraries Government Documents Department
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Annotated Bibliography of Theories of the Equation of State of Ionized Gases and Strong Electrolyte Solutions

Description: This bibliography lists 297 references on the equation of state of ionized gases and electrolyte solutions, including calculations of closely related quantities such as free energy, partition functions, o smotic pre ssure, activity coefficients, and equilibrium compositions of partially ionized systems. A subject index and a supplementary list of 42 bibliographies on plasma physics and similar topics are included. (auth)
Date: August 1, 1961
Creator: Brush, S. G. & Wensrich, C. J.
Partner: UNT Libraries Government Documents Department
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Bobcat (Program No. 56) Code Preparation Analysis on the IBM-650

Description: The BOBCAT code that is programmed for the IBM650 is described. The code facilitates the nuclear analysis of APPR-type cores by performing many of the routine calculations necessary to obtain input to various IBM-650 and IBM-704 codes. Using fuel element geometry and U/sup 235/ and B/sup 10/ loadings as input, the code prepares input to the MUFT-III and various P/sub 3/ codes as output; in addition, a large amount of detailed descriptive core data that is useful in nuclear analysis calculations is generated. (auth)
Date: August 1, 1961
Creator: Bobe, P. E. & Caton, R. L.
Partner: UNT Libraries Government Documents Department
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THE COEFFICIENT OF VOLUME EXPANSION FOR WATER AND WATER VAPOR IN THE CRITICAL REGION. Technical Report No. 6

Description: A tabulation is presented of the coefficients of volume expansion for water and for water vapor along eleven isobars in the critical region encompassed by pressures from 3000 to 4000 psia and temperatures from 690 to 750 deg F. Graphical techniques were employed to derive these values from precise P-V-T data. The over-all error in the derived values of the volume expansion coefficient was estimated to be within 5%. However, in the region of maximum values for the coefficient of volume expansion along the various isobars, the uncertainty in the derived values was estimated to be between 5 to 30%. (auth)
Date: August 1, 1961
Creator: Nowak, E. S. & Grosh, R. J.
Partner: UNT Libraries Government Documents Department
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Coextrusion Process Specifications

Description: These specifications, prepared for the N-reactor fuel, provide the framework on which the overall control and guidance of the manufacturing process shall be built.
Date: August 1, 1961
Partner: UNT Libraries Government Documents Department
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Design of the Sandia High-Altitude Sampler Rocket System (HAS)

Description: Abstract: "This report presents the characteristics incorporated in the design of a ballistic rocket system that is capable of carrying recoverable payloads varying in weight from 75 to 200 pounds to altitudes of 600,000 to 1,000,000 feet (msl)."
Date: August 1961
Creator: Bustamante, A. C. & Walker, W. E.
Partner: UNT Libraries Government Documents Department
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The Development and Evaluation of Graphite-Matrix Fuel Compacts for the HTGR

Description: >A summary of development and evaluation of graphitematrix fuel compacts for the high-temperature gas-cooled reactor is presented. The fuel compacts consist of Th-- U dicarbide particles dispersed in a high-density graphite matrix and are produced by a hot-pressing process. Compacts prepared from Th--U oxide, Th-- U silicide, and Th--U dicarbide coated with pyrolytic C were subjected to radiation and fission-product-retention testing. Results of these tests are included and are discussed in detail. (J.R.D.)
Date: August 1, 1961
Creator: Goeddel, W.V.
Partner: UNT Libraries Government Documents Department
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Development of a Ti-Al-Cb Alloy for Use at 1200-1800 F

Description: >Titanium-base alloys containing major amounts of Nb and Al are being studied to develop new high-temperature alloys of low density. Findings derived from the preparation and examination of quaternary alloys containing small additions of Sn, Hf, or Zr; high-purity ternary alloys, and ten-pound melts of Ti-l5Nb-10A1 and Ti-l7.SNb-l5Al are presented. In a number of alloys, improved tensile properties and oxidation resistance resulted from the addition of Sn, Hf, or Zr, and in some instances very high strength-density ratios were maintained up to 1800 deg F. The properties of highpurity alloys were similar to those of alloys prepared with sponge Ti. It is recommended that further effort should be directed toward the more highly alloyed compositions, including those containing Hf and Zr. (auth)
Date: August 1, 1961
Creator: McAndrew, J. B. & Simcoe, C. R.
Partner: UNT Libraries Government Documents Department
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Dimensional Behavior of the Experimental Gas-Cooled Reactor Fuel Element at Elevated Temperatures

Description: The Experimental Gas-Cooled Reactor (EGCR) fuel assemblies consist of a cluster of seven fuel elements contained in a graphite sleeve. Each element is composed of hollow cylindrical UO/sub 2/ pellets encapsulated in a type 304 stainless steel tube. The dimensional behavior of the fuel element was determined in an apparatus which simulated the thermal conditions predicted for the EGCR. Particular emphasis was placed on determining the relationship between the fuel temperature and axial expansion, the radial expansion characteristics of the fuel, the effect of cladding and fuel interaction on heating and subsequent cooling, the effect of rapid temperature excursions on the degradation of the fuel, and accumulative effects in the fuel element due to thermal cycling. An element that contains a radial gap between the cladding and the fuel pellet was found to respond to thermal cycling in the same manner that the individual components would react if subjected to the same thermal conditions and tested separately. Both the axial and radial expansion of the fuel pellet are very nearly a function of the maximum central temperature. The axial expansion of the fuel pellet column can be reduced appreciably at elevated temperatures by "dishing" the ends of the pellets. The pellets fracture radially and circumferentially upon heating, but redistribution of the fuel does not occur. If no radial gap exists between the fuel and the cladding, the expansion characteristics of the element during thermal cycling are a function of the fuel temperature, cladding temperature, and the external pressure exerted on the ele ment by the coolant stream. Thermal cycling may introduce plastic axial strains intc the cladding depending upon the details of the temperature cycle and the pressure conditions. (auth)
Date: August 1, 1961
Creator: Martin, W. R. & Weir, J. R.
Partner: UNT Libraries Government Documents Department
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Efficiency Studies with Gamma Ray Portion of Specialized Reactor-Shield Monte Carlo Program 18-0

Description: Application studies were made with Specialized Reactor-Shield Monte Carlo Program 18-0 to determine the efficiency and feasibility of calculating energy deposition due to primary core gamma rays throughout the XNJ140E-1 reactor-shield assembly. Monte Carlo results are presented in tabular form for all geometrical regions used to describe the shield. Described here is a means of obtaining adequate and valid heating rates in about 47 hours on the IBM-704 digital computer. Comparison of Monte Carlo and point kernel data are included.
Date: August 1, 1961
Creator: Capo, M. A.
Partner: UNT Libraries Government Documents Department
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Evaluation of Gas-Graphite Suspensions as Nuclear Reactor Coolants. Final Report

Description: ALL survey was made of experimental and theoretical work pertaining to the use of a suspension of graphite particles in a gas as a nuclear reactor coolant. Following a general review of the state-of-the-art and a detailed study of recent experimental data, it was concluded that present theoxy and experimental data are encouraging but inadequate as a basis for reactor design. Especially lacking are both theoretical and experimental work defining the hydrodynamic and thermal requirements for preventing the platingout of the solids from the suspension. Future work is recommended in which the stability of suspensions receives primary attention. Supporting parallel studies of basic theory, erosion, effects of nuclear radiations, and compatibility of materials, as well as development of specialized instrumentation and plant components, are also recommended. These would then be followed by experimental heat transfer and pressure drop studies to obtain correlations for reactor designm applications. (auth)
Date: August 1, 1961
Creator: Wachtell, G. P.; Waggener, J. P. & Steigelmann, W. H.
Partner: UNT Libraries Government Documents Department
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AN EXPERIMENTAL INVESTIGATION OF HIGH-FLUX FREE CONVECTION HEAT TRANSFER TO WATER UP TO NEAR-CRITICAL CONDITIONS

Description: An investigation was made to increase the basic knowledge of nucleate and film boiling heat transfer to fluids up to their critical pressures. An extensive literature survey of the subject indicated a scarcity of consistent data and an absence of proven methods for analysis. This situation led to the design and construction of experimental apparatus suitable for measuring rates of free convection heat transfer and associated temperature differences for fluid conditions up to 4000 psi and 800 deg F, with provision for visual observation. The apparatus incorporated a stainless steel system for containing the fluid. Ten-mil-diameter cylindrical and 1/8-in.-high vertical-plate platinum test sections were placed in the fluid inside a pressure vessel, 5 in. in inside diameter and 21 in. high. The pressure and temperature of the fluid envirorment were controlled by constant-volume heating of the fluid in the pressure vessel with the aid of seven zones of radiant guard heaters located between the external wall of the pressure vessel and the insulation. Each of these zones was controlled by a differential-thermocouple-sensed circuit that automatically kept the pressure vessel at a prescribed uniform temperature. Fluid pressure was measured with a deadweight tester and a 0-4000-psi Heise gauge. Fluid temperature was measured with a calibrated resistance thermometer and Mueller bridge, purchased specifically for that purpose. The heat flux in the test section was obtained from electrical measurements of the directcurrent power supplied for Joule heating. The temperature of the test section was measured by means of a resistance thermometer. The system was outgassed and filled under a vacuum with water that was deionized, degassed, and deionized again. The quality of the water was maintained during an experiment with the aid of a thermalsiphon deionizing loop which was connected to the system. The results were tabulated and plotted in terms of heat …
Date: August 1, 1961
Creator: Holt, V.E.
Partner: UNT Libraries Government Documents Department
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Final Safeguards Summary Report for the Piqua Nuclear Power Facility

Description: Summary: This report contains a description of the final design of the Piqua Nuclear Power Facility (PNPF); an outline of the test and operating procedures, and the organization and responsibilities; and a summary of the hazards and safeguards analyses that have been conducted to evaluate the safety of the facility operations.
Date: August 1, 1961
Partner: UNT Libraries Government Documents Department
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Heat-Shielded Magnetically Channeled Plasma Heat Converter

Description: A design for a thermionic converter is described which utilizes a permeable heat shield and a homogeneous magnetic field normal to the cathode and anode surfaces to minimize the radiant power loss without appreciably decreasing the electrical power output. The permeable heat shield consists of thin, close- spaced foils perpendicular to the cathode and anode surfaces. Radiant power transfer is expressed as a function of the spectral emissivities of the cathode and anode surfaces and the interfoil and interelectrode spacings. The heat shield is biased positive with respect to the cathode and anode surfaces to prevent positive ion loss, and, in conjunction with the normal homogeneous magnetic field, channels the electrons and ions to the anode. The required heat- shield positive bias is deduced and given as a function of the parameters of the converter. The energy conversion efficiencies attainable with this converter appear to be close to the Carnot efficiency. (auth)
Date: August 1, 1961
Creator: Fox, R.
Partner: UNT Libraries Government Documents Department
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HIGH TEMPERATURE OXIDATION RESISTANT COATINGS FOR TANTALUM BASE ALLOYS

Description: Aluminide and beryllide coatings were investigated for tantalunn, a binary Ta-10 W alloy, and a ternary alloy, Ta-10 Hf-5 W. Coatings were applied by dipping, packing, cold spraying, and vapor deposition. Oxidation resistance was evaluated by furnace testing, resistance heating, and flame testing. Internal hardening and diffusion effects were also studied. A Sn-Al coating was developed that had excellent oxidation resistance for 10 hours to at least 3000 deg F. Evaluation was extended to arc-plasma tests, which also showed the feasibility of protecting molybdenum and tungsten. A similar investigation was performed with a Nb alloy, which could be protected to 2500 deg F for at least 10 hours. (auth)
Date: August 1, 1961
Creator: Lawthers, D.D. & Sama, L.
Partner: UNT Libraries Government Documents Department
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Holweck Type Mollecular Pump

Description: The general design of a Holweck-type molecular pump is considered. The design consists of a stationary helical pumping groove cut inside a cylindrical bore and a closely fitting smooth cylindrical rotor spinning concentrically inside this housing. Approximate analytical expressions were obtained for the pumping speed and ultimate pressure ratio of this type pump. (J.R.D.)
Date: August 1, 1961
Creator: Sickafus, E. N.; Nelson, R. B. & Lowry, R. A.
Partner: UNT Libraries Government Documents Department
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Hydrogen Distribution and Leak Rate From the Reactor Coolant System. Test Evaluation-RNI-31A

Description: Hydrogen is injected into the coolant to a concentration of about 60 cc/ kg. The decrease in H concentration is measured as a function of time, and of the point of addition. The H may be added at the inlet or outlet sides of eithe: of two ion exchangers. The decontamination factors of these ion exchangers are not affected by the presence of the H. The time required for the H concentration to drop to half its original value varies between 118 and 172 hr. (T.F.H.)
Date: August 1, 1961
Partner: UNT Libraries Government Documents Department
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Identification of Curium-242 in Irradiated Neptunium

Description: Technical report. From Abstract : "Curium-242 was experimentally identified as a minor product of the irradiation of neptunium-237 in a nuclear reactor." From Introduction : "Determinations of the half-life, alpha energy, and daughter product of the purified curium nuclide were made in this study to confirm the identity as curium-242."
Date: August 1961
Creator: Carothers, Glenn A.
Partner: UNT Libraries Government Documents Department
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ISOMERIC CROSS-SECTION RATIOS FOR SOME (n,$gamma$) AND (/cap alpha/,XN) REACTIONS

Description: Isomeric cross section ratios for several nuclear reactions in the medium mass region were measured. The cross section ratios of isomers produced by the thermal neutron irradiation of Se/sup 60/, Rh/sup 103/, Pd/sup 106/ TE/sup 128/ and Cs/s up 133/ were measured. Isomeric cross section ratios for the formation of the isomeric pair In/sup 110/ and In/sup 110m/, produced in the Ag/ sup 107/ ( alpha ,n) and the Ag/sup 109/ ( alpha ,3n) reactions were also measured at several energies of the incoming projectile. He ions were accelerated to a maximum energy of 43 Mev. The relative amounts of the isomers produced in the reactions were determined by scintillation counting. In the case of the In/sup 110/ isomers the efficiencies of the scintillation counter for detecting each isomer were measured, so that absolute cross sections as well as cross section ratios could be determined for these isomers. The isomeric cross section ratios were also calculated theoretically using a statistical model, in which angular momentum effects were included. By comparing experimentally measured cross section ratios for the formation of isomeric pairs to the calculated ratios, information about the dependence of the nuclear level density on angular momentum was obtained. (auth)
Date: August 1, 1961
Creator: Bishop, C.T.
Partner: UNT Libraries Government Documents Department
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MAGNETIC FIELD MEASUREMENTS IN A CYLINDRICAL PINCH TUBE

Description: Magnetic field measurements in a cylindrical linear pinch tube with probes are described. Tests are performed with a discharge current frequency of 20 kilocycles in nitrogen at an initial pressure of 0.1 mm Hg. Initial capacitor voltage is varied from 1000 to 5000 volts. The magnetic field distribution, the radial current distribution, and the current density in the pinch tube are described. The discharges are concluded to be symmetric above 2000 volts. The symmetric discharges have distinct characteristics. At the start of the discharge, current flows near the outer periphery of the pinch tube. A portion of the current concentrates in a thin shell which moves toward the axis at a high velocity. The remainder of the current flows between the rapidly advancing shell and the outer radius of the pinch tube. After the formation of the first shell a second shell may form and move toward the axis. (auth)
Date: August 1, 1961
Creator: Donner, T. & Aronowitz, L.
Partner: UNT Libraries Government Documents Department
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