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REACTOR MAIN COOLANT LOOP

Description: A parametric study was made for the POPR with temperature gradients of 610 to 670 deg F and 6l0 to 684.5 deg F at organic flow rates of 17.8 x l0/sup 6/ and l4.4 x l0/sup 6/ lbs/hr, respectively; and steam turbine conditions at the throttle of 600 and 650 deg F at 800 to l200 psig. The study was made to obtain the most economical layout of the main heat transfer loop system. (B.O.G.)
Date: August 1, 1961
Creator: Terpe, G.R. & Katz, B.
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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Remote Plastic Bag Passout Unit for High-Level Radiochemical Operations

Description: A system is designed for making remote sealed-bag passouts from a multicurie-level chemistry processing enclosure. The polyethylene bags are changed remotely without exposing contaminated surfaces while always maintaining a low leak rate seal. The system employs an interchange box (passout box) attached to the chemistry enclosure. Integrated with the box is a hydraulically operated jack that raises and lowers the bags, and a welder-cutter for sealing them. A single master-slave manipulator team… more
Date: August 1, 1961
Creator: Fleischer, E. S.; Parsons, T. C. & Howe, P. W.
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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Processing of Graphite Specimens for High Temperature Irradiation by Hanford

Description: A study was made of the effects of heat treatments to 2900 and 2925 deg C and impregnations on the electric conductivity of HLM-85 and NCC-core graphite specimens. The results are graphed and tabulated. The effects of carbon pickup on the electric conductivty of impregnated samples are shown graphically. (B.O.G.)
Date: August 1, 1961
Creator: Engle, G. B.
Partner: UNT Libraries Government Documents Department
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REACTOR LABORATORY EXPERIMENTS

Description: An exposition is presented comprising a basic set of experiments in reactor physics, engineering, and technology developed by the International Institute of Nuclear Science and Engineering. Twenty-two experiments are included in a program which may be divided into groups associated with the Argonaut Reactor, the AGN-201 Reactor, and with other reactors or auxiliary equipment. (J.R.D.)
Date: August 1, 1961
Creator: Sturm, W.J. ed.
Partner: UNT Libraries Government Documents Department
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MAGNETIC FIELD MEASUREMENTS IN A CYLINDRICAL PINCH TUBE

Description: Magnetic field measurements in a cylindrical linear pinch tube with probes are described. Tests are performed with a discharge current frequency of 20 kilocycles in nitrogen at an initial pressure of 0.1 mm Hg. Initial capacitor voltage is varied from 1000 to 5000 volts. The magnetic field distribution, the radial current distribution, and the current density in the pinch tube are described. The discharges are concluded to be symmetric above 2000 volts. The symmetric discharges have distinct ch… more
Date: August 1, 1961
Creator: Donner, T. & Aronowitz, L.
Partner: UNT Libraries Government Documents Department
open access

Synthesis of Wave-Forming Networks

Description: Passive networks whose specified wave forms are given as a function of time are discussed. The wave forms may be periodic or a single pulse. Suggestions and techniques are presented which should enable a circuit designer with a basic knowledge of network synthesis procedures to obtain wave-forming networks for a wide variety of cases. (auth)
Date: August 1, 1961
Creator: LaPatra, J. W.
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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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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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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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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A Parametric Study of Certain Low-Molecular-Weight Compounds as Nuclear Rocket Propellants. v. Methane

Description: A parametric investigation was made of a series of lowmolecular-weight, high-hydrogen-content compounds as propellants for nuclear-powered rockets. The chemical compounds include H/sub 2/, NH/sub 3/, H/sub 2/0, LiH, CH/sub 4/, and CH/ sub 3/OH. A two-part computational program was carried out for each compound; the results for methane are presented in both tabular and graphic form. The results of the first part of the program are presented in static form, that is, by the conventional Mollier di… more
Date: August 1, 1961
Creator: Krieger, F.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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Process Vessel Design for Frozen-Wall Containment of Fused Salt

Description: The feasibility of the containment of a molten sodium fluoride- zirconium fluoride salt at 550 deg C in vessels with a protective inner liner of frozen salt of the same composition was demonstrated. Two different designs were used for supplying internal heat directly to the molten salt: induction heating and electrolytic heating. The test equipment was of a size practical for processing zirconiumuranium alloy reactor fuel by the Fused Salt Process. (auth)
Date: August 1, 1961
Creator: Kessie, R. W.; Gabor, J. D.; Mecham, W. J. & Jonke, A. A.
Partner: UNT Libraries Government Documents Department
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Status Report No. 1 on Clinch River Study

Description: A study of the Clinch River below Oak Ridge National Laboratory was initiated in Feb. 1960 to obtain fundamental information on the physical, chemical, and biological dy namics of this fresh-water stream which receives large volumes of low-level radioactive wastes. The fate of radioactive materials discharged to the river, the mechanisms of dispersion of radionuclides released to the river, the direct and indirect hazards of current disposal practice in the river, and the over-all usefulness of… more
Date: August 1, 1961
Creator: Morton, R.J. ed.
Partner: UNT Libraries Government Documents Department
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TWO-PHASE PRESSURE DROP IN A NATURAL CIRCULATION BOILING CHANNEL

Description: Experimental two-phase pressure drop data were obtained from a 1/4 x 2 x 60-in. vertical, uniformly heated, test section. The local volume fraction of steam was measured simultaneously with the pressure drop, thus allowing separation of the terms for hydrostatic and acceleration pressure drops from the over-all static pressure drop. The results are expressed in terms of an averge two-phase friction factor multiplier, R = DELTA P/sub TPF// DELTA P/sub L/O/sub ,/ and are co mpared with the Martin… more
Date: August 1, 1961
Creator: Hoglund, B.M.; Weatherhead, R.J. & Epperson, T.R.
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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Speed-of-control limits, 105-DR

Description: The current operating conditions at 105-DR, because of the recent Ball 3X drop, dictate temporary lower speed-of-control limits. While is si still not expected that this reactor will be limited by the speed-of- control criterion, it is felt that the limit curves have been temporarily sufficiently reduced as to warrant publication of former limits. Limit curves as a function of weighted graphite temperature for the continuous and block discharge schemes are included in this document. The two sou… more
Date: August 1, 1961
Creator: Nechodom, W. S.
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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