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WELDING AND BRAZING OF HIGH-TEMPERATURE RADIATORS AND HEAT EXCHANGERS

Description: Procedures were developed for fabricating highperformance radiators and heat exchangers for the Aircraft Nuclear Propulsion (ANP) Program. These components, which contain multitudes of tube-to-tube sheet and tube-to-fin joints, are similar in design to those under consideration for a variety of space vehicle applications. In order to ensure reliability of the tube-to-tube sheet joints, techniques producing welds of extremely high quality were used and back brazing of the welds with a suitable a… more
Date: February 20, 1962
Creator: Slaughter, G.M. & Patriarca, P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Examination of Uranium-2 w/o Zirconium Experimental Fuel Slugs Irradiated in EBR-I. Final Report-Program 6.1.11

Description: Six groups of U-2 wt% Zr fuel slugs were irradiated in the first core of the EBR-I to burnups of 0.080 to 0.189 at.% at calculated temperatures of 307 to 353 deg C. Two groups of cast specimens were found to be more dimensionally stable than four groups of wrought slugs. Of the wrought slungs, the as quenched group showed less tendency to grow than the three groups which had some annealing after quenching. Specimens at burnups of about 0.189 at.% and at 383 deg C showed the onset of swelling as… more
Date: February 1, 1962
Creator: Murphy, W. F.; Klank, A. C. & Paine, S. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division Unit Operations Section Monthly Progress Report, September 1961

Description: Nine samples of ThO/sub 2/ -UO/sub 2/ prepared as part of the solgel process development studies showed no consistent effects from small variations in several process parameters. The reaction of methane and copper oxide was studied. Engineering studies of the continuous dissolution of simulated U-Zr-Sn fuels in 6.5 M NH4F, 0.6-1.0 M NH/sub 4/NO/sub 3/, 0.1 M H/sub 2/O/sub 2/ were continued in modified 6-in.-dia. equipment. A total of 1642 kg of U from NaK bonded SRE Core I fuel rods wad dejacke… more
Date: April 1, 1962
Creator: Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Startup and Initial Testing of SM-1 Core II With Special Components

Description: The loading operation for SM-1 Core II is described. Results of startup physics measurements (Test A-300 (Series) and fission product iodine monitoring in the primary coolant are given. The SM-1 Core II initial loading progressed satisfactorily, fulfilling the predictions of the zero power experiment performed at the Alco Criticality Facility. The initial cold clean five rod bank position was 6.53 in.; the initial hot, no xenon, five rod bank position was 9.62 in.; the initial hot, equilibrium … more
Date: February 28, 1962
Creator: Moote, F. G. & Schrader, E. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Murgatroyd-an Ibm 7090 Program for the Analysis of the Kinetics of the Msre

Description: The IBM 7090 program Murgatroyd is a revised and extended version of the IBM 704 program PET-I, which solves (by a fifth-order Runge-Kutta procedure) the coupled firstorder differential equations for power, delayed neutron concentration, and temperature in a one-region reactor as a function of time, given an input reactivity variation represented by a series of linear ramps. The basic extensions were those which were necessary to include the effects of the separate heat capacities and temperatu… more
Date: April 1, 1962
Creator: Nestor, C. W. Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Supporting Analysis for Thermal Suitability of Fuel Elements for SM-1A Core I Loading

Description: A recommended SM-1A Core I loading chart was derived from available, metallurgically acceptable elements at the SM-1A and SM-1 sites. The derivation was based on local thermal and hydraulic considerations of minimum elementto- element coolant channel clearances. These clearances were determined from field inspection measurements of outer fuel plate spacing, as modified by analytical calculations of plate ripple growth during exposure to reactor operating thermal stresses. (auth)
Date: January 10, 1962
Creator: Brondel, J. O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Effects of Irradiation on Some Binary Alloys of Thorium-Plutonium and Zirconium-Plutonium

Description: A specimen of cast thorium-5 wt% plutonium and one of thorium-10 wt% plutonium were irradiated to total atom burnups of 1.9 and 2.6%, respectively, at maximum fuel temperatures of approximately 450 deg C. Both alloys displayed excellent dimensional stability with volume increases of 0.8 and 1.2% per atom per cent burnup, respectively. Three cold-rolled specimens of zirconium-5 wt% plutonium and one cold-rolled specimen of zirconium-7 wt% plutonium were also irradiated. The zirconium- plutonium … more
Date: July 1, 1962
Creator: Horak, J. A.; Kittel, J. H. & Rhude, H. V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Electrical Resistivity of Molten and Solid Thorium-Magnesium Eutetic

Description: Electrical resistivity properties of polycrystalline 39 wt % thorium-- magnesium eutectic are reported for the solid from room temperature to its melting point at 589 deg C and as a liquid from its melting point to 900 deg C. The electrical resistivity of the eutectic at the melting point was 69.5 microhm- centimeters; it decreased to a value of 64.8 microhm-centimeters at 900 C. Tantalum tubing was used to contain the alloy in the molten state. (auth)
Date: May 1, 1962
Creator: Provow, D. M. & Fisher, R. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Study of the Kinetic and Mechanical Properties of a Stabilized Beta Phase Plutonium Alloy

Description: The elements Sn, Mg, Ti, Zr, Hf, Si, Cd, and U were alloyed with plutonium to determine their effect on stabilization of the beta phase. Zirconium was found to be the ' most effective. Kinetic studies were conducted on Pu-Zr alloys having 0.24, 0.65, and 1.7 at.% Zr contents. The beta to alpha transformation in the Pu-Zr alloys was somewhat similar to that in unalloyed plutonium. The main difference being that time, temperature, transformation curves of the alloys were shifted to the right as t… more
Date: January 1, 1962
Creator: Taylor, J. M.
Item Type: Refine your search to only Thesis or Dissertation
Partner: UNT Libraries Government Documents Department
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KINETIC EXPERIMENTS ON WATER BOILERS-"A" CORE REPORT-PART II. ANALYSIS OF RESULTS

Description: The status of the analytic portion of the KEWB program at the time of completion of the spherical core experiments is summarized. Three computer programs were developed for use in this analytic effort. The first reassembles and smooths three decades of reactor power data read separately from oscillogram records of reactor excursions. It then computes the logarithmic derivative of the power, energy release, fuel solution temperature, and temperature compensated reactivity. The second program uti… more
Date: February 1, 1962
Creator: Dunenfeld, M. comp.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Corrosion Behavior of Reactor Materials in Fluoride Salt Mixtures

Description: Molten fluoride salts, because of their radiation stability and ability to contain both Th and U, offer important advantages as high-temperature fuel solutions for nuclear reactors and as media suitable for nuclear fuel processing. Both applications have stimulated experimental and theoretical studies of the corrosion processes by which molten salt mixtures attack potential reactor materials. Corrosion experiments with fluoride salts which were conducted in support of the Molten-Salt Reactor E … more
Date: September 19, 1962
Creator: DeVan, J. H. & Evans, R. B., III
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Measurements and Changes on SM-1 Core II During Period October 1, 1961 to May 30, 1962

Description: Tests at the SM-1 reactor are reported for the period October 1, 1961, to May 31, 1962. Loading changes were made in SM-1 Core II during the scheduled semiannual shutdowns in October to November 1961 and April to May 1962. Core physics tests include control rod bank calibrations, bank position at several temperature and xenon poison conditions vs core changes and energy release, shutdown neutron source decay and startup channel testing, and critical rod positions for stuck rod configurations. S… more
Date: July 1, 1962
Creator: Motte, F. G.; Best, W. C. & Kortheuer, J. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Emission Characteristics of Tantalum, Tungsten, Rhenium, and Iridium in Plasma Diodes

Description: Experimental determinations of the ionic and electronic emission characteristics of Ta, W, Re, and lr cathodes in vapor thermionic converters are compared. It is shown that Ta provides superior thermal ionization qualities at high pressure compared with W, Re, and Lr. High electronic current densities may be obtained from Cs on Re and Cs on Ir at much lower Cs vapor pressures than from Ta or W. An over-all efficiency of 19% was achieved with a Re cathode at 2440 deg K. (auth)
Date: March 15, 1962
Creator: Gust, W. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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CHEMICAL ENGINEERING DIVISION SUMMARY REPORT, JULY, AUGUST, SEPTEMBER, 1961

Description: Development activities are reported on pyrometallurgical processes including melt refining and those using liquid metal solvents. Development of processing facilities for EBR II is also reported. In other work, laboratory- and engineering-scale investigations on fluoride volatility processes were condueted, and conversion of UF/sub 6/ to UO/sub 2/ was studied. Investigations are also reported concerning the kinetics of metal ignition and oxidation, and metalwater reactions. In work associated w… more
Date: October 31, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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CORE A CRITICAL STUDIES FOR THE ENRICO FERMI ATOMIC POWER PLANT ON ZPR-III

Description: A critical studies program for the Enrico Fermi Atomic Power Plant was run with the ZPR-III fast critical facility. The objectives of this program included determination of the U enrichment required for criticality, the effect of minor variations in core and blanket composition, reactivity coefficients, control and safety rod characteristics, power distribution, spectral indices, and the reactivity worth and wave shape of the oscillator rod. The experimental program was separated into two phase… more
Date: October 1, 1962
Creator: Branyan, C.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of Subsize Izod Specimen Designs for Determining the Notch Toughness of Zircaloy-2

Description: Correlations were made on Zircaloy-2 Izod impact data and Charpy-V drop- weight data. Subsize Izod impact specimens of various geometries and notch configurations and standard ASTM Charpy-V specimens were prepared from bar and plate stock and tested. Drop-weight tests were also conducted and the NDT (nil- ductility transition) temperature was determined for 1/2 in. Zircaloy-2 plate. Results show that the impact properties of Zircaloy-2 are sensitive to hydrogen concentration, specimen and notch… more
Date: October 1, 1962
Creator: Prislinger, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Physics Division Summary Report

Description: The use and operation of the 4.5-Mev Van de Graaff generator ts descrtbed. Sputtering experiments were conducted by bombarding single crystals of electrolytic copper wtth deuterons with energies of 0.8 to 2.5 Mev. The experimental results are discussed on the basis of existing sputtering theories. The kinetic-energy distribution and Boltzmann "temperatures" of most of the fragments of cyanogen under electron impact were determined. A lower limit of 0.05 ev for this temperature'' was also determ… more
Date: January 1, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Delayed Failure Hydrogen Embrittlement of Zirconium. Summary Report, September 15, 1961 to September 14, 1962

Description: The extent to which zirconium and zirconium alloys exhibit delayed failure (static fatigue) as caused by a combination of absorbed hydrogen and applied stress was investigated. Susceptibility to time-dependent fracture was evaluated for unalloyed zirconium and Zircaloy-2 with 200 and 500 ppm hydrogen as well as for an experimental Zr Al-Sn-Mo alloy and the Canadian Zr-2.5Nb cladding material. For unalloyed zirconium and Zircaloy-2 containing up to 500 ppm hydrogen, no room-temperature, timedepe… more
Date: October 10, 1962
Creator: Weinstein, D. & Holtz, F. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effects of Temperature on Mechanical Properties of Normal Uranium Dingot

Description: Fatigue properties of normal uranium dingot for rotating beam specimens between 150 and 600 deg C are shown as S-N diagrams and are also given by an empirical equation of the form S = bN/sub m/, where S is the stress, N the number of cycIes, and b and m temperature dependent parameters. Tensile properties for temperatures ranging from 30 to 700 deg C are presented in tabular form and as stress-strain diagrams. All of the properties were found to decrease in value with increasing temperature exc… more
Date: January 1, 1962
Creator: Pederson, K. & Murphy, G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Proceedings of the 1960 Idaho Conference on Reactor Kinetics Held at Sun Valley, Idaho, October 12-14, 1960

Description: >Thirty papers are included on reactor kinetics with emphasis being placed on reactor safety and design considerations resulting from kinetic work. Information is presented on power excursion programs, reactor transfer function determination and application, reactor instability and thermal-hydraulic problems, and analytical methods in reactor kinetics. The accomplishments in the field and areas needing emphasis are discussed and summarized. Constructive suggestions are made on program direction… more
Date: July 1, 1962
Creator: Haire, J. C. & Bright, G. O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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CALCULATIONS OF THE DOPPLER COEFFICIENT OF LARGE CERAMIC-FUELED FAST REACTORS

Description: ABS>Calculations of the Doppler coefficient of large, ceramicfueled fast reactors containing plutonium were made by means of the ELMOE program to provide accurate flux calculations. The temperature-dependent cross sections of P. Greebler et al., for U/sup 238/ and Pu/sup 239/ were used. Doppler coefficients of the order of 10/sup -5/ ntermediate tem k/ C were obtained, in agreement with Greebler's results. Coefficients of carbide fueled reactors are about 0.7 of those of oxide-fueled reactors a… more
Date: August 1, 1962
Creator: Bhide, M.G. & Hummel, H.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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REACTIVITY CALIBRATIONS AND FISSION-RATE DISTRIBUTIONS IN AN UNMODERATED, UNREFLECTED URANIUM-MOLYBDENUM ALLOY RESEARCH PROGRAM

Description: Completion of zero-power critical experiments with the ORNL Health Physics Research Reactor is reported. A description is given concerning these experiments which were used to determine the critical size, fission-rate distributions, reactivity calibrations of its movable parts, the temperature coefficient of reactivity, and the reactivity effects of the presence of neutron- reflecting materials adjacent to the reactor. (J.R.D.)
Date: May 10, 1962
Creator: Mihalczo, J.T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Multigroup Calculations of Effective Delayed-Neutron Fractions, Prompt- Neutron Lifetime, and Related Kinetics Parameters. IBM-704 Program 1188/RE

Description: In the course of a recent study of kinetics parameters, it was found that RE-185, because of its limitations, was inadequate to handle the problems involved with the reactors considered. Program ll88/RE was written entirely independent of and is intended to make RE-185 obsolete. The multigroup calculations of primary interest performed by the code are as follows: the total effective delayed-neutron fraction and its distribution into six ' families'' which are characterized by their periods; the… more
Date: March 1962
Creator: Kvitek, L. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Delayed Failure Hydrogen Embrittlement of Zirconium. Quarterly Report No. 2, December 15, 1961 to March 14, 1962

Description: The purpose of this investigation is to determine the extent to which Zr and Zr alloys exhibit delayed failure (static fatigune) as caused by a combination of absorbed H and applied stress. Both notched and unnotched specimens of unalloyed Zr and Zircaloy-2 were hydrogenated to 200 ppm and 500 ppm by means of a modified Sieverts apparatus; specimens were evaluated at room temperature. Thus far, no time-dependent fracture was observed which can be attributed to the delayed failure phenomenon; it… more
Date: March 30, 1962
Creator: Weinstein, D. & Holtz, F. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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