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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… more
Date: August 1, 1961
Creator: Bobe, P. E. & Caton, R. L.
Partner: UNT Libraries Government Documents Department
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Calibration Of Bridgman Anvils, A Pressure Scale To 125 Kbars

Description: It is shown that a radial pressure gradient exists in the silver chloride when it is used as the pressure transmitting medium in Bridgman anvils. The gradient can be obviated by the use of circular sections of wire. The center of curvature of the wire hoop is made coincident with the anvil center. When the inner and outer diameters of the pyrophyllite retaining ring are 1/2 and 7/16" respectively, the pressure, P, is P = (0.725 + 0.468R) L where R is the fractional displacement from the center,… more
Date: August 1961
Creator: Montgomery, Peter W.; Stromberg, Harold; Lura, George H. & Jura, George
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… more
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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The Crystal Structure Of Cobalt Sulfate Hexahydrate

Description: Calorimetric measurements by Rao and Giauque (1960) showed some unaccountable residual entropy in crystals of [formula] at low temperatures. We have investigated the crystal structure in search of an explanation of the disorder. The resulting structure offers no possibility of disordered rings of hydrogen bonds such as were found in [formula], nor do we find any other explanation of the entropy discrepancy.
Date: August 1961
Creator: Zalkin, Allan; Ruben, Helena & Templeton, David H.
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 det… more
Date: August 1961
Creator: Goeddel, Walter 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 … more
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… more
Date: August 1, 1961
Creator: Martin, W. R. & Weir, J. R.
Partner: UNT Libraries Government Documents Department
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Double Meson Production In Proton-Deuteron Collisions. II

Description: In a previous publication we reported measurements of the momentum spectra of He<sup>3 and H<sup>3 nuclei produced in collisions of 740-MeV protons with deuterium. The He<sup>3 spectrum exhibited an anomaly in the form of a peak in the region corresponding to double pion production. For reactions resulting in a He<sup>3 the two pions (or particle) can be isotopic spin states 0 or 1; if a H<sup>3 nucleus results only 1 = 1 is allowed. We have since repeated the experiment with a new arrangement … more
Date: August 1961
Creator: Booth, Norman E.; Abnashian, Alexander & Crowe, Kenneth M.
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 Carl… more
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 prev… more
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 de… more
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 interfoi… more
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-pl… more
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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