Search Results

open access

12" SODIUM FLOW CONTROLLER. PERMANENT MAGNET COUPLING. MAGNETIC CALCULATION MANUFACTURE AND TEST RESULTS

Description: In order to retain the hermetic feature of the sodium flow controller, magnetic flux linkage of a permanent magnet coupling is used to transmit the torque produced by the operator through the pressure wall. Magnetic calculations, manufacture, and testing of this magnet coupling are described. (M.C.G.)
Date: August 18, 1961
Creator: Flator, H.E.
Partner: UNT Libraries Government Documents Department
open access

Analysis of radiation induced stresses in C Reactor graphite

Description: Figures are included which gives the necessary information on C Reactor for analysis of stress buildup in the graphite tube blocks.
Date: August 14, 1961
Creator: Yoshikawa, H. H.
Partner: UNT Libraries Government Documents Department
open access

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
open access

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
open access

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
open access

Calculated Transient Pressures Due to Impulse and Ramp Perturbations to Ventilating Systems in Buildings 3019, 3026, 3508, and 4507

Description: As part of a general hazard review survey conducted by the Chemical Technology Division of its facilities, transient pressures due to impulse and ramp perturbations to the cell ventilating systems of buildings 3019, 3026, and 4607 and the closed glove box system of 3508 were calculated. From the portions of the pressure curves above atmospheric pressure, volumes of gas outleakage were estimated; thus the amount of activity released can be calculated if an estimate of the activity concentration is available. The volumes of outleakage for all four ventilating systems were small for reasonable sizes of perturbations. For an impulse perturbation causing an instantaneous rise of +8.0 in- H/sub 2/0, the length of time above atmospheric pressure and estimated outleakages for PRFP cells in 3019 are 1.5 sec and 3.1 ft/sup 3/, respectively; for volatility cell 1 in 3019, 0.33 sec and 0.45 ft3; for cell A in 3026, 2.1 sec and 3.0 ft/sup 3/; for a glove box in 3508, 0.066 sec and 0.04 ft/sup 3/; and a cell in 4507, 0.26 sec and 0.03 ft/sup 3/. (auth)
Date: August 15, 1961
Creator: Perona, J.J.; Dunn, W.E. & Johnson, H.F.
Partner: UNT Libraries Government Documents Department
open access

Chemical Processing Department Monthly Report: July 1961

Description: This report, for July 1961 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; weapons manufacturing operation; and safety and security.
Date: August 21, 1961
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
open access

CLOSE-CAPTURE ABSORPTION SYSTEM FOR REMOTE RADIOISOTOPE CHEMISTRY

Description: Molecular sieves are used as the basic adsorber in a close-capture air recirculation system designed primarily for remote operation with master-siave equipment. A compact evaporator-dissolver unit provides a vessel for dissolution of an Al slug containing the radioactive material and provides an evaporator head under which volume reduction may be carried out within a specially prepared centrifuge cone. One movable condenser serves both operations. Resistance films of Pt provide heat for the centrifuge cone and for a jet of air impinging on the surface of the iiquid being evaporated. Moisture and acid vapors from the chemical operations are pumped from the main box and adsorbed on the molecular sieves in a separate enclosure. The dry air is then returned to the main box. Thus, by capturing vapors within a closed system and by continuously recirculating the box air through the absorbers, a reasonably dry atmosphere is maintained at all times within the chemistry enclosure, and corrosive action is effectively reduced. (auth)
Date: August 17, 1961
Creator: Spencer, N.C.; Parsons, T.C. & Howe, P.W.
Partner: UNT Libraries Government Documents Department
open access

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
open access

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
open access

Daily data sheets, UT-2 test, PT-IP-310-A-FP, D reactor

Description: This report contains daily data of the D reactor`s: outlet temperature; panelist dial; panelist base; front header pressure; and downstream probe thermocouple readings.
Date: August 17, 1961
Creator: Clinton, M. A.
Partner: UNT Libraries Government Documents Department
open access

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
open access

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
open access

THE DEVELOPMENT OF A DIRECT COUPLED, TRANSISTORIZED, SUB-MILLIMICROAMPERE CURRENT AMPLIFIER

Description: Development of a direct coupled, transistorized current amplifler is reported with sensitivities extending below the millimicroampere region of input currents. The amplifier employs a shunt feedback and exhibits reproducible characteristics. Discovery of this special effect and the design and testing employed in the incorporation of transistors into the amplifier are described. (J.R.D.)
Date: August 11, 1961
Creator: May, F.T.
Partner: UNT Libraries Government Documents Department
open access

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
open access

Development of Niobium-Uranium Alloys for Elevated-Temperature Fuel Applications

Description: As a continuation of studies reported in BMI-1400, fabrication characteristics, physical and mechanical properties, and corrosion behavior in NaK, sodium, and water of niobium--uranium binary alloys containing up to 60 wt.% uranium were investigated. Alloys were cast by a skull melting and consumable and nonconsumable arc-melting methods. Fabrication difficulties with alloys containing greater than 25 wt.% uranium were related to coring-type microsegregation during casting. Tensile tests indicated 0.2% offset yield strengths of 16,880, 22,370 and 28,600 psi for niobium2000 deg F. Additional tensile data were obtained for alloys from 1600 to 2400 deg F. Stresses to produce minimum creep rates of 0.001, 0.01, and 0.1%/hr at 1600, 1800, and 2000 deg F were also determined. Both tensile and creep strengths were found to be sensitive to oxygen content. All alloys appeared compatible with NaK at 1600 deg F and with sodium at 1500 deg F. In 600 deg F water, most of the alloys tested exhibited negligible weight changes after 336 days' exposure. Weight changes were greater after 140 days' exposure to 680 deg F water, but corrosion rates were considered satisfactory for a clad fuel. The thermal and electrical conductivities of niobium are lowered by the addition of uranium, while the thermal-expansion characteristics are essentially unaffected. Recrystallization temperatures for 90% cold-reduced niobium-4.38, -14.3, -20, -25.0, and -30 wt.% uranium alloys are 2300, 2300, 2400, 2300, and 2200 deg F, respectively. No appreciable effect of oxygen contents ranging from 100 to 1000 ppm was observed on the composition limits of the gamma immiscibility gap in the niobium-- uranium system. (auth)
Date: August 9, 1961
Creator: DeMastry, John A.; Moak, Donald P.; Epstein, Seymour G.; Bauer, Arthur A. & Dickerson, Ronnald F.
Partner: UNT Libraries Government Documents Department
open access

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
open access

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
open access

Electron Paramagnetic Resonance in Biology

Description: A review of the theories of electron paramagnetic resonance in biology is presented, including a discussion of the nature of the physical observation, followed by examples of materials of biological interest. Iq discussing these examples, information is presented in terms of the nature of the starting material under observation rather than the nature of the magnetic entities observed. The examples proceed from the simpler molecules of biological interest (metabolites, vitamins, cofactors) into the more complex materials (polymers, proteins, nucleic acids) toward cellular organelles (mitochondria, chloroplasts) and, finally, to whole cells, organisms and organs. The observation of photoinduced unpaired electrons in photosynthetic material is described and the various parameters controlling it are discussed. The basic observation is interpreted in terms of a primary photophysical act of quantum conversion.
Date: August 15, 1961
Creator: Androes, G. M. & Calvin, Melvin
Partner: UNT Libraries Government Documents Department
Back to Top of Screen