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Fabrication of the PRTR Zircaloy-2 High Pressure Process Tubes

Description: Development of a fabrication process and the manufacture of 95 PRTR process tubes demonstrates that the commercial fabrication of high quality Zircaloy-2 pressure tubing is feasible.
Date: July 31, 1959
Creator: Knecht, R. L.
Partner: UNT Libraries Government Documents Department
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Decomposition of Nitrous Oxide Final Report. Period Covered: February 19, 1959-August 18, 1959

Description: The decomposition of N/sub 2/O in a reactor tube containing various fixed-bed catalysts was investigated at 200 to 700 deg C, space velocities of 250, 1250, and 2500 vol. of gas per vol. of catalyst per hr, and various gas mixture compositions. As catalysts, En at 500 deg C and Pd at 650 deg C both gave satisfactory results. NO/sub 2/ was formed with all these catalysts, the amount increasing as the residual N/sub 2/O decreased. (C.J.G.)
Date: August 31, 1959
Creator: Zufall, J. H. & Miller, H. S.
Partner: UNT Libraries Government Documents Department
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Estimate of the Fast Effect in the Lid Tank Source Plate

Description: An estimate was made of the fast effect in the lid tank source plate. The number of fast fissions per thermal fission is 0.019. (auth)
Date: March 31, 1959
Creator: Dresner, L.
Partner: UNT Libraries Government Documents Department
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CALCULATION OF RADIAL NEUTRON-FLUX DISTRIBUTION IN EGCR LATTICE CELL

Description: The neutron flux distributions in an EGCR cell containing seven and clusters of 2.0 and 2.6a enriched uranium odde were obtained by using a one- velocity, one-dimensional P-3 solution to the neutron transport equation and adjusting fluxes in the fuel cluster in a manner which is consistent with previous comparisons of experiments and calculated distributions. Flux traverses in the outer rod perpendicular to diameter of the cluster are also presented. (auth)
Date: August 31, 1959
Creator: DeBoer, T. K.
Partner: UNT Libraries Government Documents Department
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AN EVALUATION OF MERCURY COOLED BREEDER REACTORS

Description: Under the New Reactor Concepts Evaluation Program sponsored by the United States Atomic Energy Commission. Advanced Technology Laboratories (a Division of American Radiator & Standard Sanitary Corporation) has undertaken am investigation of the technical feasibility and economic potential of the use of boiling mercury as a coolant for fast breeder reactors The investigation was performed between January 1, 1959, and October 31. 1959. This is the final report on that investigation and is submitt… more
Date: October 31, 1959
Creator: Bradfute, John O.; Battles, Donald W.; Clark, George S.; Corridan, Robert E.; Gellenbeck, Edward T.; Kavanagh, Devereux L. et al.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Unit Operations Section Monthly Progress Report for August 1959

Description: The concentration gradients of uranyl ion in aqueous and organic solutions were analyzed by taking a macro photograph of the desired gradient by monochromatic (436 m mu ) light transmitted by the solution normal to the gradient in an appropriate diffusion cell. Two Druhm runs were terminated due to malfunction of the sodium metering system and the third run was terminated when the UF/sub 6/ nozzle ruptured. Calculations of particle temperature versus time relations for the flame denitration-cal… more
Date: December 31, 1959
Creator: Bresee, J. C.; Haas, P. A.; Horton, R. W.; Watson, C. D. & Whatley, M. E.
Partner: UNT Libraries Government Documents Department
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THE HARD-CORE PINCH. PART II

Description: The toroidal version of the hard-core pinch tube is created by levitating a ring conductor inside a toroidal shell. The magnitude of induced H/ sub theta / necessary for levi-tation is small in terms of field strengths normally desired for energetic pinches. In a 3-in. glass-and-copper toroid of square cross section a 3/4-in. hollow copper ring has been levitated with a 60- cycle current of 3 kiloamperes. A 12-in stainless steel tube of round cross section is being built. The stability of nearv… more
Date: July 31, 1959
Creator: Birdsall, D.H.; Colgate, S.A. & Furth, H.P.
Partner: UNT Libraries Government Documents Department
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Zirconium Diboride, Boron Nitride, and Boron Carbide Compatibility With Austenitic Stainless Steel

Description: The compatibility of zirconium diboride, boron carbide, and boron nitride with type 304 stainless steel was evaluated as a function of temperature (1000 to 12OO deg C), time (1-3 hr). Appropriate loadings of the boron compounds and stainless steel powder were blended and fashioned into a compact powder metallurgically. Each compact was roll clad into a plate and subsequently heat treated at a temperature equal to the initial sintering temperature. Metallographic examination of the fabricated an… more
Date: July 31, 1959
Creator: Cherubini, J. H. & Leitten, C. F. Jr.
Partner: UNT Libraries Government Documents Department
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SER Temperature Coefficient

Description: Experimentally determine the overall isothermal temperature coefficient of the SER up to the design operating temperatures.
Date: December 31, 1959
Creator: Johnson, J. L.
Partner: UNT Libraries Government Documents Department
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Stored Energy: Growth and Annealing Status of Graphite Moderator in the BNL Research Reactor. Final Report

Description: The present sthtus, past annealing procedures and experiences, future annealing procedures, annealing sehedule, revised annealing procedure (1958), procedure for combating a graphite fire in fuel channel, high-temperature stored energy, and graphite burning experiments are reportcd for the BNL Research Reactor. The following subjccts are discussed in the appendixes: control of radiation damage in a graphitc reactor; annealing of graphite moderator structure in the BNL; annealing operation in BN… more
Date: October 31, 1959
Partner: UNT Libraries Government Documents Department
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URANIUM ALLOY POWDERS BY DIRECT REDUCTION OF OXIDES

Description: A process is outlined for the production of uranium alloy powders by co- reduction of mintures of uranium oxide and alloy element oxides. The reduction of mechanical mintures of the oxides of uranium and alloy element with calcium in a sealed reaction vessel is shown to produce powder wtth a variation in particle composition, although of consistert composition over various size fractions. The particular alloy systems which are considered are uranium--nickel, uranium-- chromium, uranium --molybd… more
Date: October 31, 1959
Creator: Myers, R.H. & Robins, R.G.
Partner: UNT Libraries Government Documents Department
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Fuel Elements Conference Held at Gatlinburg, Tennessee, May 14-16, 1958

Description: The fuel element conference provided a favorable medium for presentation and discussion of recent developments in the field of solid fuel elements. The conference was designed to replace the more general Metallurgy Information Meetings held annually in the past. The scope of the meeting embraced the design fabrication, performance, and material problems of fuel elements. (W.D.M)
Date: October 31, 1959
Partner: UNT Libraries Government Documents Department
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PROCEEDINGS OF THE FRENCH-AMERICAN CONFERENCE ON GRAPHITE REACTORS, HELD AT BROOKHAVEN NATIONAL LABORATORY , NOVEMBER 12 TO 15, 1957

Description: Twenty-eight of the thirty-five papers presented at the conference are included with discussions. Abstracts of the remaining seven papers are given. The seven sessions were devoted to: radiation effects on graphite, nuclear properties of graphitc, graphite lattice reactivities, chemistry of graphite, chemical reactions between liquid Na and Zr, slug canning fer the ORNL Graphite Reactor, and critical assemblies. Separate abstracts have been prepared for each of the twentyeight papers. (T.R.H.)
Date: October 31, 1959
Partner: UNT Libraries Government Documents Department
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Quarterly Progress Report for the Period July 1 to September 30, 1958

Description: An evaluation and the resulting conclusions of work performed are given for each project in which definitive progress was made. The principle progress consisted of: obtaining promising fuel fabrication results from production scale investigations of simplified UO/sub 2/ preparations methods, presintering operation elimination, increasing pellet densities and reductions of UO/sub 2/ losses; successfully brazing a ninety-five inch long experimental fuel subassembly in which all joints, including … more
Date: October 31, 1959
Creator: Garbe, R. W. & Walchli, H. E.
Partner: UNT Libraries Government Documents Department
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Sodium Reactor Experiment (Sre) Shielding Evaluation for Thermal Neutron Streaming at Reactor Vessel Coolant Pipe Penetrations

Description: The experimental program performed in the SRE auxiliary and main primary galleries was part of a program to determine the adequacy of the shielding configuration for the SRE. The work discussed in this report is concerned with analysis of neutron streaming at coolant pipe penetrations of the reactor vessel, analysis of the shielding required, testing and evaluation of recommended shielding, and measurement and correlation of neutron streaming in labyrinths with theory. The activation analysis m… more
Date: October 31, 1959
Creator: Anderson, F. D.
Partner: UNT Libraries Government Documents Department
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Development of Uranium Nitride-Stainless Steel Dispersion Fuel Elements

Description: In research in support of the GCRE, procedures for the fabrication of stainless steel-clad flat-plate fuel elements having a core of 28 w/o UN dispersed in an iron-18 w/o chromium--14 w/o nickel--2.5 w/o molybdenum matrix were developed. The preparation of UN and its compatibility with the components of the matrix alloy were studied. The UN for the program was prepared by nitriding uranium metal at 850 C and then dissociating the U/sub 2/N/sub 3/ produced to UN in a vacuum at 1300 C. In compati… more
Date: July 31, 1959
Creator: Paprocki, S. J.; Keller, D. L.; Cunningham, G. W. & Foulds Jr., A. K.
Partner: UNT Libraries Government Documents Department
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Monthly Progress Report for the Period September 1 to 30, 1958

Description: A 95-inch experimental Yankee sub-assembly was successfully brazed at 1890 plus or minus 10 for three hours then furnace cooled. All of the joints, outside ferrules, and control rod rubbing strips showed a brazed flllet. Dimensional surveys and joint strength studies indicate that two brazing techniques appear feasible for subassemblies. Codings for computers for use in core design problems are described. A series of criticality calculations for the three water-to-metal volume ratios of the Yan… more
Date: October 31, 1959
Creator: Garbe, R. W. & Walchli, H. E.
Partner: UNT Libraries Government Documents Department
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APPLIED HEALTH PHYSICS SEMI-ANNUAL REPORT FOR JULY 1956-DECEMBER 1956

Description: Routine monitoring procedures are summarized. Based on samples collected by continuous air monitors, the wcekly average value for air contamiration in the laboratory area was 1.98 x 10/sup -12/ mu c/cc. Radioactive fall-out was determined by measuring the total activity and total number of particles collected on gum paper fall-out trays. Two peak periods of activity in July and September were concluded to be the result of weapons tests. Meteorological data are tabulated. Data are included from … more
Date: October 31, 1959
Partner: UNT Libraries Government Documents Department
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ELK RIVER REACTOR. Quarterly Project Report for December 1958 January- February 1959

Description: Design and construction are proceeding satisfactorily. Fuel capsule irradiation studies are progressing, and preparation of specifications for fuel elements and assemblies is almost complete. Other design, development, and construction progress is reported. Instrumentation developments are described. Reactor physics studies are reported. (For preceding period see AECU-4013.) (T.R.H.)
Date: October 31, 1959
Partner: UNT Libraries Government Documents Department
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HIGH TEMPERATURE PROPERTIES OF URANIUM AND ITS ALLOYS

Description: Data are presented on the mechanical and physical properties of high- purity and normal uranium and for a range of dilute uranium alloys at temperatures up to 700 deg C. The results of thermal conductivity and thermal expansion determinations for a range of alloys are discussed, and some results on the latent heat of fusion and volume change on melting are presented. Results of dilute alloy creep tests are reported and correlated with thermal cycling data and resistence to swelling under irradi… more
Date: October 31, 1959
Creator: McIntosh, A.B. & Heal, T.J.
Partner: UNT Libraries Government Documents Department
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VARIABLE MODERATOR REACTOR DEVELOPMENT PROGRAM. Quarterly Progress Report No. 1

Description: Development of the boiling water UO/sub 2/ fueled Variable Moderator Reactor (VMR) is conducted under contract for the USAEC. The initiation and progress of work under Phase I of the contract, Physics and Kinetic Analysis and Initial Evaluation,'' and the preparation for Phase II, Critical Experiment and Analysis of Results,'' are reported. A hydrodynamic flow sheet representing the sequence of calculations for the BOCH program was prepared. A preliminary block diagram of the kinetics model of … more
Date: August 31, 1959
Partner: UNT Libraries Government Documents Department
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NUCLEAR BATTERY--THERMOCOUPLE TYPE. Quarterly Progress Report No. 8 for October 1, 1958 to December 31, 1958

Description: A demonstration battery containing an 880-curie polonium-2l0 heat source was constructed and tested. The battery initially had an open circuit voltage of 23.6 volts, a maximum output of 161 milliwatts, and an overall efficiency of 0.57%. Details for the construction of the battery generator are given. (For preceding period see MLM-CF-58-4-59.) (auth)
Date: October 31, 1959
Creator: Blanke, B.C.
Partner: UNT Libraries Government Documents Department
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