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THE EXPERIMENTAL DESIGN FOR BeO IRAADIATION EXPERIMENTS ORNL 41-8 AND ORNL 41-9

Description: The experimental plan for irradiating BeO pellets in Experiments ORNL 41- 8 and ORNL 41-9 was chosen in accordance with the principles of experimental design. The design is known by statisticians as a 2/sup 5/ factorial experiment confound'' in six replications. Five variables---size, density, grain size, temperature and time--are controlled at two levels to form the basic 2i factorial experiment. The sixth variable, neutron flux, is introduced by confounding on higher-order interactions. An ex… more
Date: July 18, 1962
Creator: Gardiner, D.A.
Partner: UNT Libraries Government Documents Department
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Experimental Breeder Reactor-II (EBR-II) Shield Design

Description: A description of the EBR-II shield and the methods employed in arriving at the final design are presented. The major shield design problems for that reactor are enumerated and discussed. (auth)
Date: September 1, 1962
Creator: Grotenhuis, M.; McArthy, A. E. & Rossin, A. D.
Partner: UNT Libraries Government Documents Department
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Administration of ORNL Research Reactors

Description: Organization of the ORNL Operations division for administration of the Oak Ridge Research Reactor, the Low Intensity Testing Reactor, and the Oak Ridge Graphite Reactor is described. (J.R.D.)
Date: August 20, 1962
Creator: Casto, W. R.
Partner: UNT Libraries Government Documents Department
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Tests of Bearing Materials for the Experimental Through-Tubes in the Egcr

Description: The four experimental through-tubes provided in the Experimental Gas Cooled Reactor will extend directly through the core of the reactor and penetrate both the upper and lower pressure vessel heads. Each tube is anchored in an upper head nozzle and the bottom end is allowed to slide in a lower head nozzle. This lower nozzle is basically a T'' section that provides bottom access to the through-tube and a side access for the piping which connects the throughtube to the experimenter's cell. Due to… more
Date: July 16, 1962
Creator: MacPherson, R. E. & Smith, A. M.
Partner: UNT Libraries Government Documents Department
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SNAP Programs: Task 6--Fuel Technology Development Program. Quarterly Progress Report No. 7, April 1 Through June 30, 1961

Description: Progress made in the development of isotope power sources for thermoelectric and thermionic conversion to electrical energy is reported. The Heavy Elements Processing Facility for processing americium and fabricating americium capsules for irradiation was opened and hot operation was begun. Modifications to the americium purification system were completed and checkout operations were begun. Process specifications were established for dissolution of the irradiated capsules and the major equipmen… more
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
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RADIOISOTOPES AND RADIATION APPLICATIONS. Quarterly Progress Report No. 12

Description: Continued research is reported in the areas of intrinsic radioactive tracers for industrial process control and the effects of structural factors on radioinduced graft polymerization. The use of Be-- Po neutron sources for production of short-lived isotopes is being investigated. Data are included on the effects of target volume, high-Z scattering media, target-isotope concentration, and macroscopic cross-section on speciflc and total activation produced with a 10-curie source. Research on graf… more
Date: April 18, 1962
Creator: Sunderman, D.N. ed.
Partner: UNT Libraries Government Documents Department
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H4LM Graphite

Description: A commercial graphite useful in nuclear reactor construction is described. A survey of all currently available sources on chemical and physical properties was made and the information listed. Some data on cost and available sizes are also included. (auth)
Date: July 5, 1962
Creator: Merryman, R. G.; Wagner, P. & MacMillan, D. P.
Partner: UNT Libraries Government Documents Department
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Nonequilibrium Ionization in Magnetohydrodynamic Generators

Description: The steady state ionization of a gas in which the electrons are hot and the atoms cool is investigated. The rate equations governing ionization, excitation, recombination, and de-excitation are solved for a model system using rate coefficients appropriate to the Cs atom. Included are all processes involving free electrons as well as spontaneous emission and resonance trapping of radiation. No incoming radiation is assumed, and the system is assumed large compared with a collisional mean free pa… more
Date: January 1, 1962
Creator: BenDaniel, D.J. & Tamor, S.
Partner: UNT Libraries Government Documents Department
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A Theoretical Study of Destructive Nuclear Bursts in Fast Power Reactors

Description: The calculation of destructive nuclear bursts in fast reactors by an improved Bethe-Tait method, which, for purposes of calculation, neglects propagation of the pressure wave is described. TMen exact numerical calculations for hydrodynamic and neutronic conditions during the power burst are performed in order to assess the importance of this neglect. (auth)
Date: February 1, 1962
Creator: Jankus, V. Z.
Partner: UNT Libraries Government Documents Department
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Pathfinder Atomic Power Plant Technical Progress Report, January 1962-March 1962

Description: S>Progress is reported on the research and development program being performed in connection with the design of the Pathfinder Atomic Power Plant. The topics covered include: fuel material cladding, bonding, and irradiation testing; heat transfer and fluid flow; fuel element manufacturing research and development; low-enrichment superheater fuel element design; mechanical studies of control rods, guide tubes, and control rod drives; reactor physics; and reactor and system dynamics. (C.H.)
Date: June 30, 1962
Partner: UNT Libraries Government Documents Department
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GUIDE TO NUCLEAR POWER COST EVALUATION. VOLUME 4. FUEL CYCLE COSTS

Description: Information on fuel cycle cost is presented. Topics covered include: nuclear fuel, fuel management, fuel cost, fissionable material cost, use charge, conversion and fabrication costs, processing cost, and shipping cost. (M.C.G.)
Date: March 15, 1962
Partner: UNT Libraries Government Documents Department
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CLIP 1--AN IBM-704 PROGRAM TO SOLVE THE P-3 EQUATIONS IN CYLINDRICAL GEOMETRY

Description: A second order form of the cylindrical P-3 equations is obtained for the case of an isotropic source. The boundary conditions and numerical method are discussed. Input preparation and operating instructions are included. (auth)
Date: May 1, 1962
Creator: Anderson, B.; Davis, J.; Gelbard, E.; Jarvis, P. & Pearson, J.
Partner: UNT Libraries Government Documents Department
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Propane Vibrational Analysis

Description: Using the group vibratibn method of McMurry, the normal frequencies and coordinates of propane and three of its symmetrical deuterium substituted compounds were obtained. The force constants used were taken from a variety of previous works on hydrocarbons. The results give reasonable agreements with the experimental frequency and mode assignments of others. (auth)
Date: June 12, 1962
Creator: Marshall, G. D.
Partner: UNT Libraries Government Documents Department
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NIGHTMARE-AN IBM 7090 CODE FOR THE CALCULATION OF GAMMA HEATING IN CYLINDRICAL GEOMETRY

Description: The NIGHTMARE program calculates the gamma-dose rate at any point in or near a reactor by means of the NDA buildup-factor method. The source distributton is obtained from a two-group, two-dimensional diffusion code (EQUIPOISE-2). Seven gamma-energy groups are used. As many as nine different concentric cylindrical regions may be considered, but only radial variation of attenuation and buildup properties is permdtted. Two schemes of estimating buildup factors through a succession of materials are… more
Date: February 26, 1962
Creator: Tobias, M.L.; Vondy, D.R. & Lietzke, M.P.
Partner: UNT Libraries Government Documents Department
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A System for Generating Gamma Ray Cross Section Data for Use with the IBM-7090 Computer

Description: A system for generating detailed tables of gamma ray cross section data has been devised for use on the IBM7090 computer. This sy;tem obviates the preparation of large amounts of cross section data. It also provides a scheme for rapid access to these tabulated values. (auth)
Date: May 16, 1962
Creator: Penny, S. K.; Emmett, M. B. & Trubey, D. K.
Partner: UNT Libraries Government Documents Department
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Stress and Deflection of Boiler Fuel Element Boxes

Description: Equations were derived by strain-energy methods for analyzing the stress and deflection in the boiler fuel element boxes used in the Pathfinder nuclear reactor. These boxes are of two types, both constructed of Zircaloy lI. One box is approximately 5 in. sq. The second is approximately 10 1/2 in. sq divided internally into four compartments (5 in. sq) by a cruciform control-rod guide structure. Stress and deflection in the box walls are caused by pressure differences across the walls. The equat… more
Date: April 13, 1962
Creator: Vlies, L. E.
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF PLUTONIUM-BEARING FUEL MATERIALS. Progress Report, October 1-December 31, 1961

Description: Continued effort is reported on preparation and characterization of PuO/ sub 2/ and UO/sub 2/-- PuO/sub 2/ mixtures. Sintering and characterization of pellets for irradiation tests was emphasized, and efforts were also devoted to plasma torch production of spherical PuO /sub 2/ and coating of oxide materials. PuO/sub 2/ produced by the oxalate process from low concentration feed contains agglomerates which are not readily broken down, while that produced from normal feed contains larger agglome… more
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
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EGCR EXPERIMENTAL LOOPS, PRELIMINARY DESIGN REPORT

Description: The EGCR was designed to accommodate up to four gascooled experimental loops plus several experimental fuel elements in the open core. Two of the loops will utilize 51/2-in.-O.D. stainless steel tubes passing through the core along an axis which is about 17 in. from the central axis of the core. The other two loops will utilize 91/2-in.-o.d. tubes about 68 in. from the central axis. Inherent safety in the design, facility design, primary loop design, auxiliary systems and equipment design, prim… more
Date: March 27, 1962
Creator: Neill, F.H. & Michelson, C.
Partner: UNT Libraries Government Documents Department
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Dissociation and Ionization of H$Sub 2$$Sup +$ by Electrons and Protons

Description: <><DSN>16:009503<ABS>Included are summaries of studies of: DCX-1 operation and performance; DCX-2 design and engineering; plasma physics; vacuum arcs; ion production, acceleration, and injection; plasma theory and computations; magnetics; and vacuum system techniques. Separate abstracts were prepared for the eight sections. (B.O.G.) 9504(Faye unscannable abstract)
Date: January 24, 1962
Creator: Alsmiller, R. G., Jr.
Partner: UNT Libraries Government Documents Department
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Quarterly Status Report on LAMPRE Program for Period Ending May 20, 1962

Description: During the report period 110 Mw-hr of operation were completed by LAMPRE I at various power levels, and observations were made of control element performance and reactivity losses. Metallographic examination of a Core I capsule having 120 Mw-hr of irradiation exposure disclosed no major attack. Core II utilizes Ta alloy melts and 13 fuel melts. Starting materials for Core II capsules are tabulated. In research and development a gamma-ray conversion television was used to observe the flow of mol… more
Date: June 1, 1962
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF PLUTONIUM-BEARING FUEL MATERIALS. Progress Report for Period January 1 through March 31, 1962

Description: During this reporting period, particular effort was of aced on powder blending and pellet sintering studies prior to irradiation sample fabrication, and, subsequently, the production and characterization of the pellets slated for irradiation. Also, PuO/sub 2/ and UO/sub 2/-PuO/sub 2/ characterization studies were continued, and new techniques are being developed. Specifically, dynamic moisture pickup determinations on PuO/sub 2/ were made in moist air, N, and CO/ sub 2/ atmospheres using a reco… more
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
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TWO AUXILIARY CODES FOR USE WITH RENUPAK

Description: Two IBM-7090 codes were written to aid the user of the neutron moments method code RENUPAK. One code computes and punches response function input cards for RENUPAK or NIOBE (another neutron transport code). The second code reads RENUPAK flux tapes and prints out a compact edit including dose rate as a function of distance. (auth)
Date: August 10, 1962
Creator: Trubey, D.K.
Partner: UNT Libraries Government Documents Department
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Studies of Nuclear Resonant Absorption of Gamma Rays. Quarterly Report No. 4 Covering Period June 1, 1961 to August 31, 1961

Description: The effect of polarizing mngnetic field intensity on the nuclear resonant absorption was studied by varying the field strength at a 1-mc Co/sup 57/ source from 0 to 1000 gauss while keeping the absorber between the poles of a magnet having a fixed field of 800 gauss. The rates of resonance absorption change with field intensity were greatest in the region of 300 to 1000 gauss, and the% nuclear resonant absorption for 1000-gauss fields was 8.5 and 26% for perpendicular and parallel fields, respe… more
Date: February 23, 1962
Creator: Ezop, J. J.
Partner: UNT Libraries Government Documents Department
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