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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
Preparation of Charge Materials for Ornl Electromagnetic Isotope Separators
SEPARATORS. C. W. Sheridan, H. R. Gwinn, and L. O. Descriptions are given of procedures, techniques, and equipment used to prepare charge materials for electromagnetic isotope separators at ORNL. Data on ion outputs during processing, charge consumption rates, and process efficiencies are given for 54 elements. (auth)
Date:
August 1, 1962
Creator:
Sheridan, C W; Gwinn, H R & Love, L O
Object Type:
Report
System:
The UNT Digital Library
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
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
SIZE ANALYSIS OF PARTICULATES FOUND IN AIR AT HANFORD PLUTONIUM FABRICATION FACILITIES
A study was made on the characteristics of radioactively contaminated air at Hanford work locations. One of the main objectives in this study is to define the size of particular air contamination in plutonium handling facilities. In addition to characterizing the particulate contamination, it is desirable to know the normal background particle size distribution. Data are summarized on general particle size distribution and radioactive particle distribution at two Hanford plutonium fabrication facilities. (auth)
Date:
August 1, 1962
Creator:
Selby, J.M.
Object Type:
Report
System:
The UNT Digital Library
CALCULATIONS OF THE DOPPLER COEFFICIENT OF LARGE CERAMIC-FUELED FAST REACTORS
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 at the same fuel enrichment. Effective coarse- group elastic-removal cross sections for light elements are tabulated. It appears that, with tabulations of this sort as a guide, coarse-group sets of cross sections can be constructed to give adequate accuracy in calculations of Doppler coefficients without use of ELMOE. (auth)
Date:
August 1, 1962
Creator:
Bhide, M.G. & Hummel, H.H.
Object Type:
Report
System:
The UNT Digital Library
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
Methods and Techniques of Fallout Studies Using a Particulate Simulant
The fallout hazard and protection factors in current use for large groups of buildings, i.e., urban residential areas, business districts, industrial complexes, government centers, Atomic Energy Commission facilities, and academic and medical institutions, are largely unsubstantiated by experimental evidence. These data are important for personnel protection on a national basis in the event of war and on a local basis in the event of certain types of nuclear accidents. The need for such information is discussed and methods for obtaining it are suggested. The methods suggested should provide a cross check of the data obtained on isolated structures under actual fallout conditions with the data from studies that made use of methods such as distributed point sources and a moving single-point source (as used in the Mobile Radiological Measurement Unit, Civil Effects Test Operations) to simulate actual fallout fields and with data from other studies in which predicted values of fallout protection were calculated from strictiy theoretical considerations. (auth)
Date:
August 1, 1960
Creator:
Lee, W. & Borella, H.M.
Object Type:
Report
System:
The UNT Digital Library
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
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
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
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
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
The Specific Heat of Dysprosium Metal Between 0.4 and 4 K
Submitted to Illinois Inst. of Tech., Chicago. A He/sup 3/ cryostat was built to measure the specific heat of rare earth metals which have a component, at low temperatures, attributable to the electrons in the incomplete 4f shell. The specific heat of dysprosium from 0.4 to 4.2 deg K was measured. Pertinent theories about specific heats are outlined. The apparatus included the cryostat, vacuum and He/sup 3/ systems, calorimeter, carbon thermometer, heater, and magnetic thermometer. The experimental procedure is described and results are presented in graphic and tabular form. The specific heat rose sharply below 1 deg K. An anomalous hump was centered about 2.35 deg K. (M.C.G.)
Date:
August 1, 1962
Creator:
Guenther, R. A.
Object Type:
Thesis or Dissertation
System:
The UNT Digital Library
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
X-Ray Diffraction Study of Cs$sub 3$ZrF$sub 7$
None
Date:
August 1, 1962
Creator:
Robbins, G. D. & Burns, J. H.
Object Type:
Report
System:
The UNT Digital Library
THE CRYSTAL STRUCTURE OF LiCuCl$sub 3$ /center dot/ 2H$sub 2$O
None
Date:
August 1, 1960
Creator:
Vossos, P. H.; Fitzwater, D. R. & Rundle, R. E.
Object Type:
Report
System:
The UNT Digital Library
AN EVALUATION OF MATERIALS OF CONSTRUCTION FOR THE SULFLEX AND ZIRFLEX PROCESSES
concentration is not greater than four molar and the nitric acid greater than five molar. In addition, core dissolutions should be done below the boiling point, and heat transfer surface termperatures during core dissolution should be maintained below 240 deg F. Carpenter 20 is probably less satisfactory for Sulfex service because of selective weld attack. Neither Ni-o-nel, 309 SCb, or 304L is a satisfactory construction material for uninhibited Zirflex solutions. Cupric ion lowers the corrosion rate of 309 SCb to 30--40 mils per year, but is not a satisfactory inhibitor for 304L or Ni-o-nel. (auth)
Date:
August 1, 1962
Creator:
Katz, H. & Isler, R.
Object Type:
Report
System:
The UNT Digital Library
Ionium, Uranium-232, and Thorium-228 Properties, Applications and Availability
Charts are given which present information on the properties, sources, and uses of Th/sup 230/, Th/sup 228/, and U/sup 232/ They also compare these properties with competitive isotopes. (M.C.G.)
Date:
August 1, 1960
Creator:
Rohrmann, C.A.
Object Type:
Report
System:
The UNT Digital Library
Laboratory-Scale Demonstration of the Fused Salt Volatility Process
The feasibility of processing enriched irradiated zirconium--uranium alloy fuel by the fused salt-fluoride volatility procedure has been demonstrated in laboratory tests with fuel having a burnup of over 10%. Uranium recoveries were greater than 99% and decontamination factors for radioactive fission products were 10/sup 6/ to 10/sup 6/. The UF/sub 6/ product contained significant quantities of nonradioactive impurities; additional work in this area is needed. (auth)
Date:
August 1, 1962
Creator:
Cathers, G. I.; Jolley, R. L. & Moncrief, E. C.
Object Type:
Article
System:
The UNT Digital Library
THERMIONIC CONVERTERS FOR COMPACT NUCLEAR POWER PLANTS
A brief review of several thermionic nuclear power plants leads to the conclusion that the in-core concept is the most practical and useful system for space applications. Fundamental considerations indicate that emitter temperatures from 1500 to 1900 deg C are required for this concept, and that the high work function refractory metals are the best electrode materials for achieving the required performance and lifetime at these temperatures. The analytical and experimental technology developed for systematically defining the optimum materials and operatlng conditions is described, along with the significance of the experimental results obtained. These results have shown that the required performance can be obtained with the elementary cesium vapor diode converter. It was also shown that impurities cause pronounced effects on both performance and lifetime, and that their suppression or controlled utilization is an important aspect of the present approach. (auth)
Date:
August 1, 1962
Creator:
Rasor, N.S. & Weeks, C.C.
Object Type:
Report
System:
The UNT Digital Library
The Salt Cycle Process
The Salt Cycle Process is a nuclear fuel processing approach designed for application in compact facilities located at the reactor sites. Irradiated UO/sub 2/ fuels would be processed through a brief sequence of steps and partially purified UO/sub 2/ or UO/sub 2/--PuO/sub 2/ powders recovered, suitable for refabrication into fuel elements. The major steps of the process are the dissolution of uranium oxides in molten NaCl--KCl eutectic by chlorination to form soluble uranyl chloride and the reduction of uranyl chloride to UO/sub 2/, which separates as a solid. The preferred method of reduction is the electrolytic method, which yields UO/sub 2/ as a conveniently handled, adherent deposit on the cathode. Means are described for separation of Pu from U and for co-deposition of the Uo. Also included are discussions of the probable nature of the U and Pu species present in the molten salt, side reactions in which uranyl chloride may participate, and the influence of certain variables on the properties of the UO/sub 2/ produced. (auth)
Date:
August 1, 1960
Creator:
Benedict, G.E.; Lyon, W.L.; Mudge, L.K.; Swanson, J.L. & Walling, M.T. Jr.
Object Type:
Report
System:
The UNT Digital Library
An Out-of-Pile Electron Irradiation Circulating Loop for Fouling Studies
An out-of-pile electron irradiation circulating loop was developed to study the problem of fuel element fouling in organic cooled reactors. Unlike pyrolytic loops and capsules, the irradiation loop operates at temperatures, pressures, fluid dynamics, geometry, and radiation damage which closely resemble reactor conditions. The loop is run in conjunction with the 4-kw -- 6-Mev electron linear accelerator. The thickness of the fouling film deposited in the irradiation cell is measured and the film subjected to chemical analysis. Test results showed that clean coolant did not foul; reactor coolant (Core II) with particulate matter fouled; heaviest film was found in the radiation area; and lower fouling occurred at high velocity. (auth)
Date:
August 1, 1962
Creator:
Mengelkamp, R. A.; Hudson, P. S. & Hillyer, J. C.
Object Type:
Report
System:
The UNT Digital Library
THE ELECTRIC-DIPOLE GAMMA-RAY STRENGTH FUNCTION FOR HEAVY EVEN-EVEN NUCLEI
None
Date:
August 1, 1962
Creator:
Carpenter, R.T.
Object Type:
Report
System:
The UNT Digital Library