ANHARMONIC POTENTIAL CONSTANTS AND THEIR DEPENDENCE UPON BOND LENGTH (open access)

ANHARMONIC POTENTIAL CONSTANTS AND THEIR DEPENDENCE UPON BOND LENGTH

Empirical study of cubic and quartic vibrational force constants for diatomic molecules shows them to be approximately exponential functions of internuclear distance. A family of curves is obtained, determined by the location of the bonded atoms in rows of the periodic table. Displacements between successive curves correspond closely to those in Badger's rule for quadratic force constants (for which the parameters are redetermined to accord with all data now available). Constants for excited electronic and ionic states appear on practically the same curves as those for the ground states. Predictions based on the diatomic correlations agree with the available cubic constants for bond stretching in polyatomic molecules, regardless of the type of bonding involved. Implications of these regularities are discussed. (auth)
Date: August 1, 1961
Creator: Herschbach, D.R. & Laurie, V.W.
Object Type: Article
System: The UNT Digital Library
REACTOR MAIN COOLANT LOOP (open access)

REACTOR MAIN COOLANT LOOP

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.
Object Type: Report
System: The UNT Digital Library
Annotated Bibliography of Theories of the Equation of State of Ionized Gases and Strong Electrolyte Solutions (open access)

Annotated Bibliography of Theories of the Equation of State of Ionized Gases and Strong Electrolyte Solutions

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.
Object Type: Report
System: The UNT Digital Library
Doppler Broadening of the Low Energy Total Neutron Cross Section of Pu-241 (open access)

Doppler Broadening of the Low Energy Total Neutron Cross Section of Pu-241

None
Date: August 1, 1961
Creator: Simpson, O. D. & Marshall, N. H.
Object Type: Report
System: The UNT Digital Library
Remote Plastic Bag Passout Unit for High-Level Radiochemical Operations (open access)

Remote Plastic Bag Passout Unit for High-Level Radiochemical Operations

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 teamed with the above units handles all operations. (auth)
Date: August 1, 1961
Creator: Fleischer, E. S.; Parsons, T. C. & Howe, P. W.
Object Type: Report
System: The UNT Digital Library
Dimensional Behavior of the Experimental Gas-Cooled Reactor Fuel Element at Elevated Temperatures (open access)

Dimensional Behavior of the Experimental Gas-Cooled Reactor Fuel Element at Elevated Temperatures

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 …
Date: August 1, 1961
Creator: Martin, W. R. & Weir, J. R.
Object Type: Report
System: The UNT Digital Library
A Computer Analysis for Complex Sodium Iodide Gamma Spectra (open access)

A Computer Analysis for Complex Sodium Iodide Gamma Spectra

None
Date: August 1, 1961
Creator: Mollenauer, J. F.
Object Type: Report
System: The UNT Digital Library
Processing of Graphite Specimens for High Temperature Irradiation by Hanford (open access)

Processing of Graphite Specimens for High Temperature Irradiation by Hanford

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.
Object Type: Report
System: The UNT Digital Library
REACTOR LABORATORY EXPERIMENTS (open access)

REACTOR LABORATORY EXPERIMENTS

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.
Object Type: Report
System: The UNT Digital Library
MAGNETIC FIELD MEASUREMENTS IN A CYLINDRICAL PINCH TUBE (open access)

MAGNETIC FIELD MEASUREMENTS IN A CYLINDRICAL PINCH TUBE

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 characteristics. At the start of the discharge, current flows near the outer periphery of the pinch tube. A portion of the current concentrates in a thin shell which moves toward the axis at a high velocity. The remainder of the current flows between the rapidly advancing shell and the outer radius of the pinch tube. After the formation of the first shell a second shell may form and move toward the axis. (auth)
Date: August 1, 1961
Creator: Donner, T. & Aronowitz, L.
Object Type: Report
System: The UNT Digital Library
Synthesis of Wave-Forming Networks (open access)

Synthesis of Wave-Forming Networks

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.
Object Type: Report
System: The UNT Digital Library
AN EXPERIMENTAL INVESTIGATION OF HIGH-FLUX FREE CONVECTION HEAT TRANSFER TO WATER UP TO NEAR-CRITICAL CONDITIONS (open access)

AN EXPERIMENTAL INVESTIGATION OF HIGH-FLUX FREE CONVECTION HEAT TRANSFER TO WATER UP TO NEAR-CRITICAL CONDITIONS

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 deg F, with provision for visual observation. The apparatus incorporated a stainless steel system for containing the fluid. Ten-mil-diameter cylindrical and 1/8-in.-high vertical-plate platinum test sections were placed in the fluid inside a pressure vessel, 5 in. in inside diameter and 21 in. high. The pressure and temperature of the fluid envirorment were controlled by constant-volume heating of the fluid in the pressure vessel with the aid of seven zones of radiant guard heaters located between the external wall of the pressure vessel and the insulation. Each of these zones was controlled by a differential-thermocouple-sensed circuit that automatically kept the pressure vessel at a prescribed uniform temperature. Fluid pressure was measured with a deadweight tester and a 0-4000-psi Heise gauge. Fluid temperature was …
Date: August 1, 1961
Creator: Holt, V.E.
Object Type: Report
System: The UNT Digital Library
Development of a Ti-Al-Cb Alloy for Use at 1200-1800 F (open access)

Development of a Ti-Al-Cb Alloy for Use at 1200-1800 F

>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.
Object Type: Report
System: The UNT Digital Library
CALCULATIONS FOR ZPR-VII FLUX-TRAP REACTORS WITH HEAVY WATER-MODERATED CORES (open access)

CALCULATIONS FOR ZPR-VII FLUX-TRAP REACTORS WITH HEAVY WATER-MODERATED CORES

None
Date: August 1, 1961
Creator: Pennington, E.M.
Object Type: Report
System: The UNT Digital Library
Holweck Type Mollecular Pump (open access)

Holweck Type Mollecular Pump

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.
Object Type: Report
System: The UNT Digital Library
HIGH TEMPERATURE OXIDATION RESISTANT COATINGS FOR TANTALUM BASE ALLOYS (open access)

HIGH TEMPERATURE OXIDATION RESISTANT COATINGS FOR TANTALUM BASE ALLOYS

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-plasma tests, which also showed the feasibility of protecting molybdenum and tungsten. A similar investigation was performed with a Nb alloy, which could be protected to 2500 deg F for at least 10 hours. (auth)
Date: August 1, 1961
Creator: Lawthers, D.D. & Sama, L.
Object Type: Report
System: The UNT Digital Library
A Parametric Study of Certain Low-Molecular-Weight Compounds as Nuclear Rocket Propellants. v. Methane (open access)

A Parametric Study of Certain Low-Molecular-Weight Compounds as Nuclear Rocket Propellants. v. Methane

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 diagram, in which specific enthalpy is plotted against specific entropy, with cross plots of temperature, pressure, and molecular weight. The results of the second part of the program are presented in dynamic form by a series of diagrams in which specific impulse is plotted against pressure, with cross plots of chamber temperature, exhaust temperature, and rocket-nozzle area. It was assumed that the propellant gas, starting with a nonzero chamber velocity, maintained instantaneous chemical equilibrium composition as it expanded isentropically through a de LavaI nozzle. (auth)
Date: August 1, 1961
Creator: Krieger, F.J.
Object Type: Report
System: The UNT Digital Library
Bobcat (Program No. 56) Code Preparation Analysis on the IBM-650 (open access)

Bobcat (Program No. 56) Code Preparation Analysis on the IBM-650

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.
Object Type: Report
System: The UNT Digital Library
Process Vessel Design for Frozen-Wall Containment of Fused Salt (open access)

Process Vessel Design for Frozen-Wall Containment of Fused Salt

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.
Object Type: Report
System: The UNT Digital Library
Status Report No. 1 on Clinch River Study (open access)

Status Report No. 1 on Clinch River Study

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 this river for radioactive waste disposal purposes will be studied. In formation obtained will have important implications for problems involving large-scale environmental contamination such as the over- all diluent capacity of fresh-water environments for the continuous input of large volume low-level radioactive wastes and the long-term indirect impact of radioactive contamination on such an environment. White Oak Creek, which drains the site ot Oak National Laboratory, flows into the Clinch River, a tributary of the Tennessee River. The Clinch and Tennessee Rivers are described and available data on the physical, chemical, and biological conditions of the rivers are summarized. Data are included from preliminary studies on the properties of water and bottom sediments, studies on radionuclide interactions with minerals and river sediment, biological studies …
Date: August 1, 1961
Creator: Morton, R.J. ed.
Object Type: Report
System: The UNT Digital Library
TWO-PHASE PRESSURE DROP IN A NATURAL CIRCULATION BOILING CHANNEL (open access)

TWO-PHASE PRESSURE DROP IN A NATURAL CIRCULATION BOILING CHANNEL

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 Martinelli-Nelson correlation, the LottesFlinn correlation, and a correlation combining that of Martinelli-Nelson and a flowrate parameter. The ranges of variables include: pressure from 150 to 600 pstg; power density from 17.2 to 94.5 kw/liter of coolant; sub-cooling from 4.8 to 25.7 deg F; exit qualities from 0.009 to 0.065; exit steam volume fraction from 0.19 to 0.77; and velocities from 2.56 to 3.43 fps. (auth)
Date: August 1, 1961
Creator: Hoglund, B.M.; Weatherhead, R.J. & Epperson, T.R.
Object Type: Report
System: The UNT Digital Library
Technical letter: Dribble-4 generalized stratigraphic section for the Tatum dome area, Lamar County, Mississippi (open access)

Technical letter: Dribble-4 generalized stratigraphic section for the Tatum dome area, Lamar County, Mississippi

None
Date: August 1, 1961
Creator: Eargle, D.H.
Object Type: Report
System: The UNT Digital Library
Texas Attorney General Opinion: WW-1101 (open access)

Texas Attorney General Opinion: WW-1101

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether the county may legally enter into a contract pertaining to the furnishing of hospital services for the employees of a county hospital.
Date: August 1, 1961
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Optimization of Emission-Limited Thermionic Generators, Paper (open access)

Optimization of Emission-Limited Thermionic Generators, Paper

No Abstract. There is a duplicate copy.
Date: August 1, 1961
Creator: Schock, Alfred
Object Type: Article
System: The UNT Digital Library