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Use of Analog Computers for Simulating the Movement of Isotopes in Ecological Systems
None
Date:
January 24, 1962
Creator:
Neel, R. B. & Olson, J. S.
Object Type:
Thesis or Dissertation
System:
The UNT Digital Library
Supporting Analysis for Thermal Suitability of Fuel Elements for SM-1A Core I Loading
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.
Object Type:
Report
System:
The UNT Digital Library
Chemical Technology Division, Unit Operations Section Monthly Progress Report, June 1961
An interfacial viseometer was built for use in an interfacial phenomena study. Installation of a 6-in.-ID foam separation column system was completed. The dispersiondrying-sintering characteristics of six low-nitrate batches of thoria sol material were studied. The average effective porosity of the CuO pellets used for reactor helium purification was determined to be 0.0545 for H/ sub 2/ transport and 0.0526 for CO transport. In continuous Zirflex dissolution studies, no H/sub 2/O/sub 2/ decomposition was observed when 10% H/sub 2/O/sup 2 was fed into boiling dissoivent through a water-cooled nozzle and the oxygen concentration in the scrubbed off-gas could be used to control the H/sub 2/O/sub 2/ concentration in the dissolver. The free fluoride in Zirflex solutions must be maintained above 1 molar in order to prevent uranium precipitation at low concentrations of uranium even though the F/sup -//U ratio exceeds 100. Chopped stainless steel-clad UO/sub 2/ sections were leached in a 4 stage pyrex leacher model using 6, 7, and 8 M nitric acid as the dissolvent. The temperature distribution expected within fuel elements consisting of square arrays of tubes was calculated for shipping conditions assuming heat to be transferred only by radiation. HETS values were calculated for uranium stripping …
Date:
January 23, 1962
Creator:
Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Object Type:
Report
System:
The UNT Digital Library
A Study of the Kinetic and Mechanical Properties of a Stabilized Beta Phase Plutonium Alloy
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 the zirconium concentration increased. It was determined that the amount of beta phase retained at room temperature increased as the zirconium concentration increased. The minimum amount of Zr needed to stabilize the beta phase of plutonium at room temperature was determined to be 2.0 at.%. A 2.4 at.% Zr addition stabilized the beta phase of plutonium at atmospheric pressure from room temperature to 265 deg C. During mechanical property testing it was determined that the stabilized beta Pu-2.4 at.% Zr alloy was brittle from room temperature to 230 deg C. Both tensile and compression strengths of the beta stabilized alloy were greater than the unalloyed beta phase of plutonium. A brittle-ductile transition was noted between 130 …
Date:
January 1, 1962
Creator:
Taylor, J. M.
Object Type:
Thesis or Dissertation
System:
The UNT Digital Library
Determination of Heavy Water Purity by Infrared Absorption
The practical application of heavy water purity determination by infrared absorption spectroscopy using standard laboratory equipment was demonstrated in connection with the operation of heavy water-moderated Special Power Excursion Reactor Test (SPERT II) Facillty at the NRTS. (auth)
Date:
January 16, 1962
Creator:
Abernathey, R. M. & Morgan, T. D.
Object Type:
Report
System:
The UNT Digital Library
THE THEORY AND MEASUREMENT OF CRITICALITY
ABS>The measurable properties of a critical assembly (e.g.. fission, capture, and leakage rates; neutron-per-fission ratios; bare/Cd-covered reaction rate of-atios; danger eoefficients; etc.), whose judicious use completely defines tbcneutron economy in the assembly, are discussed. Require ments regarding the internal consisteney of these of:deasured quantities are reviewed. lt is concluded that theoretical analysis of the assembly must both reproduce the gross experimental results and reflect the internal consistency of the data. Only thermal systems fueled with U/sup 235/ and U/sup 238/ are considered. (T.F.H.)
Date:
January 1, 1962
Creator:
Kelber, C.N.
Object Type:
Report
System:
The UNT Digital Library
Physics Division Summary Report
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 determined for the mass spectrometer. A statistical theory of nuclear forces was developed in close analogy with the statistical mechanics of Gibbs. The theory of Byers and Yang was improved by removing the special assumption of cylindrical symmetry and the assumption of independentparticle motion. The safe assumption of time-reversal invariance was substituted for both. The quantum of trapped flux was found to be independent of the shape of the superconducting ring. The effective charge 2e was seen to result from the two-fold degeneracy induced by time-reversal invariance. It was observed that the same considerations which apply to the problem of flux quantization can be used to elucidate the gauge invariance of the theory of Bardeen, Cooper, and Schrieffer. Differences of total cross sections at high energies …
Date:
January 1, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Delayed Failure Hydrogen Embrittlement of Zirconium. Quarterly Report No. 1, September 15, 1961 to December 14, 1961
A research program to determine the extent to which Zr and Zircaloy-2 exhibits delayed fnilure (static fatigue) as caused by absorbed H/sub 2/ and applied stress is outlined. Dynamic tensile tests were carried out on Zr and Zircaloy-2 without and wlth 200 ppm H/sub 2/. Preliminary results of a delayed failure investigation suggest that Zr containing 200 ppm H/sub 2/ is relatively insensitive to delayed ailure at room temperature up to 900 hr. (D.L.C.)
Date:
January 1, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Effects of Temperature on Mechanical Properties of Normal Uranium Dingot
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 except that at about 350 deg C they showed some irregularities. These irregularities can possibly be explained by the fact that at lower temperatures deformation by twinning predominates while slipping predominates sbove 350 deg C. (auth)
Date:
January 1, 1962
Creator:
Pederson, K. & Murphy, G.
Object Type:
Report
System:
The UNT Digital Library
Critical Studies of a Fast Reactor Core Containing Depleted Uranium and Sodium as Diluents. (ZPR-III Assembly 36)
Critical studies were performed with a metallic, fast reactor core designed to snvestigate the effects of replacing highly absorbing U/sup 238/ diluent with high-scattering, lowabsorbing sodium diluent. The fuel was 15.7 wt% enriched U/sup 235/ and the core contained 18.2 vol% sodium and 12.68 vol% stainless steel. The experimental program was designed to measure the effect of the material replacement on spectral indices, which consisted of the standard fission ratios, foil irradiations, and a large number of central reactivity coefficients. Other measurements included the Rossi- alpha , radial fission traverses, and edge reactivity worths of a few samples. (auth)
Date:
January 1962
Creator:
Gasidlo, J. M.; Long, J. K. & McVean, R. L.
Object Type:
Report
System:
The UNT Digital Library
THERMONUCLEAR DIVISION PROGRESS REPORT, FEBRUARY 1, 1961-OCTOBER 31, 1961
None
Date:
January 24, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
MOLTEN-SALT REACTOR PROGRAM PROGRESS REPORT FOR PERIOD FROM MARCH 1 TO AUGUST 31, 1961
The Molten Salt Reactor Experiment design, component development, and engineering analysis is discussed. Materials studies for the Molten-Salt Reactor Program including metallurgy, in-pile tests, chemistry, engineering research, and fuel processing are described. (M.C.G.)
Date:
January 19, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Calculation of Distance Factors for Power and Test Reactor Sites
>Reference information and guidance on procedures and basic assumptions related to reactor siting are presented which can be used to calculate distance requirements consistent with current siting practices. A single method of competing distances and exposure for a general class of reactors is giveo. (J.R.D)
Date:
January 1, 1962
Creator:
DiNunno, J. J.; Anderson, F. D.; Baker, R. E. & Waterfield, R. L.
Object Type:
Report
System:
The UNT Digital Library
FACILITY FOR PHOTOGRAPHING IN-PILE MELTDOWN EXPERIMENTS IN TREAT
Techniques and equipment were developed for photographing of samples during in-pile meltdown experiments in TREAT. The design and materials for the transparent meltdowm facility are described. The procedures for assemblys insertion in TREAT, removal, and disassembly are outlined. (M.C.G.)
Date:
January 1, 1962
Creator:
Golden, G.H.; Dickerman, C.E. & Robinson, L.E.
Object Type:
Report
System:
The UNT Digital Library
Nonequilibrium Ionization in Magnetohydrodynamic Generators
The steady state ionization of a gas in which the electrons are hot and the atoms cool is investigated. The rate equations governing ionization, excitation, recombination, and de-excitation are solved for a model system using rate coefficients appropriate to the Cs atom. Included are all processes involving free electrons as well as spontaneous emission and resonance trapping of radiation. No incoming radiation is assumed, and the system is assumed large compared with a collisional mean free path but optically thin except for resonance radiation. The fractional ionization is computed for a range of electron temperatures and Cs densities of interest in MHD studies. It is found that there are reasonable conditions of temperature and density under which the ionization is close to that which would prevail if the system were in equilibrium at the electron temperature. At lower temperatures or densities, the ionization decreases but is still much greater than that appropriate to the gas temperature. (auth)
Date:
January 1, 1962
Creator:
BenDaniel, D.J. & Tamor, S.
Object Type:
Report
System:
The UNT Digital Library
Dissociation and Ionization of H$Sub 2$$Sup +$ by Electrons and Protons
<><DSN>16:009503<ABS>Included are summaries of studies of: DCX-1 operation and performance; DCX-2 design and engineering; plasma physics; vacuum arcs; ion production, acceleration, and injection; plasma theory and computations; magnetics; and vacuum system techniques. Separate abstracts were prepared for the eight sections. (B.O.G.) 9504(Faye unscannable abstract)
Date:
January 24, 1962
Creator:
Alsmiller, R. G., Jr.
Object Type:
Report
System:
The UNT Digital Library
SPECIFIC HEAT DATA ANALYSIS PROGRAM FOR THE IBM 704 DIGITAL COMPUTER
A computer program was developed to calculate the specific heat of a substance in the temperature range from 0.3 to 4.2 deg K, given temperature calibration data for a carbon resistance thermometer, experimental temperature drift, and heating period data. The speciftc heats calculated from these data are then fitted by a curve by the methods of least squares and the specific heats are corrected for the effect of the curvature of the data. The method, operation, program details, and program stops are discussed. A program listing is included. (M.C.G.)
Date:
January 1, 1962
Creator:
Roach, P.R.
Object Type:
Report
System:
The UNT Digital Library
INDUSTRIAL CRITICALITY MEASUREMENTS ON ENRICHED URANIUM AND PLUTONIUM. PART II
ABS>A series of neutron multiplication measurements made on sub-critical systems containing enriched uranium and plutonium is presented. These measurements involve both aqueous and metal systems. (auth)
Date:
January 10, 1962
Creator:
Schuske, C.L.; Bell, C.L.; Bidinger, G.H. & Smith, D.F.
Object Type:
Report
System:
The UNT Digital Library
EBWR Reactor Pressure Vessel Revisions for Instrumentation and Increased Steam Output
The procedures developed and utilized for the addition of connections to the EBWR pressure vessel after three yesrs of intermittent operation at the 20- Mw(t) design heat output are described. Major nozzle connections to the pressure vessel were made during two separated periods and under different conditions of vessel content. The details of the conversion sre discussed under the following topics: nozzle design, preparations, and nozzle installation. Diagrams and photographs are included. Radioactive particulate material transport and trapped radioactive particulate matter sre discussed. (M.C.G.)
Date:
January 1, 1962
Creator:
Kettles, T.L. & Balai, N.
Object Type:
Report
System:
The UNT Digital Library
Primary Plant Self-Actuated Relief Valve Operation. Core I, Seed 3. Test Evaluation. Section 2
A test was conducted on August 12 to 13, l961, on the operation of the four reactor coolant loop relief valves and the four purification system relief valves. The results indicated proper operation. (D.L.C.)
Date:
January 12, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Numerical Analysis of Neutron Resonances
Neutron resonances are analyzed numerically by determining the resonant energies, the total widths, and the neutron widths of the resonances. It was assumed that the total cross section can be represented by the sum of single- level Breit-Wigner formulas, with interference between resonance and potential scattering but no interference between resonances; that the Doppler broadening is represented by a Gaussian function; and that the instrument resolution is represented by a Gaussian function. Gauss' method was used to reduce the nonlinear problem to one in which linear methods can be applied. Some unusual techniques were used for evaluating the integrals in the function for calculating the transmission. Two programs for analyzing transmission data to obtain the parameters of the resonances were written for the IBM 7090 computer. The first program is a shape analysis for determining the resonant energies, the total widths, and the neutron widths of the resonances. This program analyzes the transmission data for as many as six resonances at once. The second program is an area analysis for determining the neutron widths of the resonances for assumed total widths. This program analyzes transmission data containing as many as 20 resonances at once. (auth)
Date:
January 10, 1962
Creator:
Atta, S.E. & Harvey, J.A.
Object Type:
Report
System:
The UNT Digital Library
Pathfinder Atomic Power Plant Analog Simulator.
The steady-state and dynamlc characterlstics of the Pathfinder systems were simulated on a dual-console Pace Analog Computer. The derivation of the system equations, the assumptions involved, their numerical evaluation, and their conversion to analog circuitry are described. The Pathfinder system is unique because of the internal nuclear superheater, and controlled, forced recirculation. In simulating this system the following major assumptions were maden the reactor is a boiling-water type; moderated and cooled with saturated, light water; pressurized between 400 and 800 psiai and has a neutron flux distribution that is spatially invariant. All the importanit non-linearities are retained, thus permitting accurate solutions of large system disturbances. The neutron kinetics equations, with their six groups of delayed neutrons, are simulated with power feedbacks through reactor pressure, steam flow, core inlet subcooling, and fuel- element temperature. Particular attention ls devoted to the accurate simulation of fuel-element heat transfer; the reactor pressure-control system, which operates the turbine inlet valves; and the effect of core inlet subcooling, sinee these were found to have pronounced effects on reactor performance. The transient temperatures at the superheater hot spot and exit are generated. Enough flexibility ss included, so that all important disturbanees possible in the actual plant can …
Date:
January 31, 1962
Creator:
Crimmins, D. H.; Mohr, D. & Stone, J. T.
Object Type:
Report
System:
The UNT Digital Library
CHARACTERIZATION OF UO$sub 2$ POWDERS. Fourth Quarterly Report, July 10, 1961-October 10, 1961
Studies are described of UO/sub 2/ powders to determine the relation between properties of the powders and sinterability. The main effort during the period was devoted to correlation of the powder particle size distribution with the sintered density of pellets. The pressure applied during the green forming step of pellet production is shown to have a varied and considerable effect on ceramic particle size distribution in the pellets. (J.R.D.)
Date:
January 20, 1962
Creator:
Carpenter, J.F.; Kuhlman, C.W. & Nelson, R.A.
Object Type:
Report
System:
The UNT Digital Library
HEXAFLUORIDES OF MOLYBDENUM, TUNGSTEN AND URANIUM. II. REACTIONS WITH LIQUID AND GASEOUS DINITROGEN TETROXIDE
Molybdenum and tungsten hexafluorides form the solids nitrosylium pentafluoroxymolybdate(VI) and -tungstate(VI), respectively. Uranium hexafluoride gives nitrosylium hexafluorouranate(V) STANOUF/sub 6/!, the same salt that it forms with nitric oxide. (auth)
Date:
January 29, 1962
Creator:
Geichman, J. R.; Smith, E. A.; Swaney, L. R. & Ogle, P. R.
Object Type:
Report
System:
The UNT Digital Library