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COMP: a BASIC language nonlinear least-squares curve fitting program
COMP is an interactive nonlinear least squares routine written in BASIC language and used to obtain estimates of parameters in nonlinear functions and to approximate their associated statistical errors. The program uses the linearizing (or Taylor Series) expansion of partial derivatives outlined in Draper and Smith, (1966, pp. 267 to 270). Therefore, partial derivatives must be supplied (as well as the function) by the user for any new models not currently contained in the programs. When a linearizing method is used to estimate parameters in a nonlinear model, all the usual procedures of linear regression theory can be applied. However, the results so obtained are only valid insofar as the linearized form approximates the true model. All of the statistics computed by COMP should be viewed with this restriction in mind. The output of COMP includes the variance-covariance matrix, t-tests for parameters, Von Neumann's ratio, observed, predicted and residual values, the error mean square, and an optional procedure to evaluate heteroscedasticity.
Date:
November 1, 1977
Creator:
Thomas, J. M.; Cochran, M. I.; Watson, C. R. & Eberhardt, L. L.
System:
The UNT Digital Library
Pion correlations as a function of atomic mass in heavy ion collisions
The method of two pion interferometry was used to obtain source-size and lifetime parameters for the pions produced in heavy ion collisions. The systems used were 1.70 {center dot} A GeV {sup 56}Fe + Fe, 1.82 {center dot} A GeV {sup 40}Ar + KCl and 1.54 {center dot} A GeV {sup 93}Nb + Nb, allowing for a search for dependences on the atomic number. Two acceptances (centered, in the lab., at {approximately} 0{degrees} and 45{degrees}) were used for each system, allowing a search for dependences on the viewing angle. The correlation functions were calculated by comparing the data samples to background (or reference) samples made using the method of event mixing, where pions from different events are combined to produce a data sample in which the Bose-Einstein correlation effect is absent. The effect of the correlation function on the background samples is calculated, and a method for weighting the events to remove the residual correlation effect is presented. The effect of the spectrometer design on the measured correlation functions is discussed, as are methods for correcting for these effects during the data analysis. 58 refs., 39 figs., 18 tabs.
Date:
November 26, 1989
Creator:
Chacon, A.D.
System:
The UNT Digital Library
Status Report on the Argonne Advanced Research Reactor
The interim design and development status is reported. The scope of the work was limited to conceptual design studies supported by critical experiments plus heat transfer and hydraulic tests. Design criteria, facility and site, reactor, core geometry and composition, fuel elements, reflector, core and reflector support structure, reactor vessel, control and instruments, primary coolant systems, secondary coolant system, auxiliary systems, experimental facilities, building layout and construction, plant ventilation, heating and air conditioning, critical experiments, reactor physics, heat transfer studies, and shieldings are discussed. (M.C.G.)
Date:
November 1, 1961
Creator:
Lennox, D. H.; Barts, E. W.; Batch, R. V.; Beyer, F. C.; Jorgensen, G. L.; Kelber, C. N. et al.
System:
The UNT Digital Library
Magnetic field, closed orbit, and energy measurement in the Bevatron
This report provides the information necessary for a better evaluation of particle energy in the Bevatron. Previously, the nominal magnetic field value and radius were used to calculate the value for the kinetic energy of the particle. This value was good to a few percent. Today, more and more experimenters would like to know the energy to a more precise value. To this end, corrections to the measured magnetic field values and the radial closed orbit are provided.
Date:
November 1, 1981
Creator:
Crebbin, K. C.
System:
The UNT Digital Library
Hanford Environmental Dose Reconstruction Project Monthly Report
This monthly report summarizes the technical progress and project status for the Hanford Environmental Dose Reconstruction Project being conducted at Pacific Northwest Laboratory under the direction of a Technical Steering Panel.
Date:
November 1, 1989
Creator:
Dennis, B.S. (comp.)
System:
The UNT Digital Library
BRAZING OF CERAMICS. Progress Report
Brazing alloys such as 48 Ti-48 Zr-4 Be (wt%) and 49 Ti-49 Cu-2 Be (wt%) have been found to readily flow on oxide and graphite ceramics. Two demonstrati on fuel element assemblies were fabricated to illustrate the usefulness of these procedures for nuclear applications. One of these assemblies contained graphite tubes and end caps which were brazed to a molybdenum hanger. The second demonstration fuel element was composed of a compartmented aluminum oxide plate to which aluminum oxide cover plates were brazed. (R.J.S.)
Date:
November 1, 1962
Creator:
Fox, C.W.
System:
The UNT Digital Library
Cost Function Studies for Power Reactors
A function to evaluate the cost of electricity produced by a nuclear power reactor was developed. The basic equation, revenue = capital charges + profit + operating expenses, was expanded in terms of various cost parameters to enable analysis of multiregion nuclear reactors with uranium and/or plutonium for fuel. A corresponding IBM 704 computer program, which will compute either the price of electricity or the value of plutonium, is presented in detail. (auth)
Date:
November 1, 1961
Creator:
Heestand, J. & Wos, L.T.
System:
The UNT Digital Library
Fusion utilization projections in the United States energy economy
The following topics are discussed in some detail in this report: (1) applications of fusion energy, (2) fusion implementation in the US energy system, (3) reactor performance requirements, (4) technology for electric applications, and (5) technology for synthetic fuel/chemical applications. (MOW)
Date:
November 1, 1979
Creator:
Powell, J.R. & Fillo, J.A.
System:
The UNT Digital Library
Enhanced durability and reactivity for zinc ferrite desulfurization sorbent
AMAX Research Development Center (AMAX R D) has been investigating methods for enhancing the reactivity and durability of the zinc ferrite desulfurization sorbent. Zinc ferrite sorbents are intended for use in desulfurization of hot coal gas in integrated gasification combined cycle (IGCC) or molten carbonate fuel cell (MCFC) applications. For the present program, the reactivity of the sorbent may be defined as its sulfur sorption capacity at the breakthrough point and at saturation in a bench-scale, fixed-bed reactor. Durability may be defined as the ability of the sorbent to maintain important physical characteristics such As size, strength, and specific surface area during 10 cycles of sulfidation and oxidation.
Date:
November 14, 1988
Creator:
Jha, Mahesh C. & Berggren, Mark H.
System:
The UNT Digital Library
Digital SLIFER Recorder, Model A. [Underground nuclear explosions]
The Digital SLIFER Recorder (DSR) is an instrument that records a time-varying frequency signal in the range from 700 kHz to 1500 kHz with an amplitude greater than 200 mV. This signal is referenced to an input fiducial marker, and recording is initiated by an increase in the frequency of the signal. The primary purpose of this instrument is to record data from the SLIFER system. The DSR records 512 samples after the record trigger signal, with a sample interval of 50 ..mu..s (for a total recording time of 25.55 ms). The measurement essentially uses a 20-cycle period-averaging counter technique.
Date:
November 1, 1977
Creator:
Breding, D.R.; Fogel, D.; Loukota, J.J.; Worthen, G.S. & Watterberg, J.P.
System:
The UNT Digital Library
Results of the radiological survey at 12 Long Valley Road, Lodi, New Jersey (LJ054)
Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extracting process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 12 Long Valley Road, Lodi, New Jersey (LJ054), was conducted during 1985 and 1986. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different …
Date:
November 1, 1989
Creator:
Foley, R.D.; Floyd, L.M. & Carrier, R.F.
System:
The UNT Digital Library
New Solutions of the Boltzmann Equation for Monoenergetic Neutron Transport in Spherical Geometry
Solutions of the Boltzmann equation for monoenergetic neutron transport in spherical geometry are derived which are respectively singular and regular at the center of the sphere. A few specific partial singular solutions are presented. The regular solutions in spherical geometry are constructed by superposition of solutions in plane geometry which belong to the same k. Finally, the solutions are compared with their representations by a series of spherical harmonics. (D. L.C.)
Date:
November 17, 1961
Creator:
Kofink, W.
System:
The UNT Digital Library
ACORN: a computer program for plotting fault trees. [In FORTRAN for CDC Cyber 74]
A description and user instructions are presented for ACORN, a FORTRAN computer program for drawing fault trees. ACORN analyzes the input logical structure of a fault tree and provides data for CalComp plot of the tree. AND, OR, and INHIBIT gates are permitted, and basic events are drawn as diamonds, circles, or houses. Each component (gate or basic event) can have a descriptive label within a rectangle attached to the top of its respective symbol. Tree logic is input as a set of FORTRAN statements, each defining a gate in terms of logical operations of the components input to it. ACORN develops the logical structure of the tree from the input statements. The tree's physical structure is developed by assigning relative spatial coordinates to the logical relationships between a gate and its inputs. ACORN provides input data checking, a printer plot of the fault tree, and plotting data for a CalComp model 763 plotter. The program is operational on a CONTROL DATA CYBER 74 computer. 2 figures, 1 table.
Date:
November 1, 1977
Creator:
Carter, J. L.
System:
The UNT Digital Library
Investigation of impurity radiation from a well diganosed, laser heated plasma sample. Final report
The results are described of an experimental and theoretical program designed to measure the relative intensities of line radiation from various ionization stages of carbon and helium impurities added to a deuterium plasma, and to relate the observed line intensity ratios to the plasma temperature. A deuterium sample plasma is produced and heated to a temperature of 2 to 7 eV at an electron density of 5 x 10/sup 16/ cm/sup -3/. The plasma parameters are monitored at various discrete times during the plasma decay using the Thomson scattering system. Simultaneously, the same sample volume is observed in the visible region of the spectrum using a streak camera coupled to a spectrograph. A continuous record of the plasma visible spectrum is thus obtained during the plasma time history, with at one specific time a data point on the plasma parameters, n/sub e/ and T/sub e/. Modifications were made to the plasma sample facility to shorten the duration of the preionization current and to increase its magnitude. This modification accomplished the desired effect of increasing the electron density in the heated plasma to 5 x 10/sup 16/, essentially obtaining full filling density. Additional insulation was added to the solenoid and satisfactory …
Date:
November 1, 1977
Creator:
Crawford, E.; Quimby, D.; Hoffman, A. & Pietrzyk, Z.A.
System:
The UNT Digital Library
Efficiencies of gas neutralizers for multi-MeV beams of light negative ions
Measurements are reported of the neutral and charged particle fractions produced by running beams of Li/sup -/, C/sup -/, O/sup -/, and Si/sup -/ at energies up to 7 MeV through gas cells of N/sub 2/, Ar, or CO/sub 2/. We discuss the implications of these measurements for the design of neutralizers to produce high energy light atom beams for heating or current drive in tokamaks.
Date:
November 1, 1981
Creator:
Grisham, L. R.; Post, D. E.; Johnson, B. M.; Jones, K. W.; Barette, J.; Kruse, T. H. et al.
System:
The UNT Digital Library
General multi-configuration Hartree--Fock program: MCHF77. [In FORTRAN (double precision) for IBM 360 and 370]
This technical report contains a listing of a general program for multi-configuration Hartree--Fock (MCHF) calculations, including its documentation. Several examples are given showing how the program may be used. Typical output for several cases is also presented. This program has been tested over an extended period of time for a large variety of cases. This program is written for the IBM 360 or 370 in double-precision arithmetic.
Date:
November 1, 1977
Creator:
Fischer, C F
System:
The UNT Digital Library
Mass Transfer Coefficients and Interfacial Area in a One Stage Pulse Column
Over-all mass transfer coefficients were determined independently of the interfacial area by considering the operation of the pulse column to be a stage- wise process. The calculated coefficients describe only the operation of the pulse column for the free rise of organic droplets through a stage, since in the downstroke the aqueous phase passes through the organic phase in the form of rivulets preferentially wetting the plates. The driving force for transfer was based on the aqueous phase concentrations. The mass transfer coefficient was found to increase when the interfacial tension was reduced. Two factors appear to affect the mass transfer coefficient as the pulse frequency is changed and are: a) recycle or backmixing which tends to decrease the coefficient through a reduction of acetic acid in both phases and thereby increases the interfacial tension, and b) turbulence which enhances the coefficient by reducing the continuous film resistance. The first is important at or near the lower flooding limit, but the latter is the controlling factor at higher frequencies. (D.L.C.)
Date:
November 1, 1960
Creator:
Konopik, A. E. & Burkhart, L.
System:
The UNT Digital Library
Investigations of the Natural Fission Reactor Program. Progress report, October 1976--September 1977
During Fiscal Year 1977, efforts of the Natural Fission Reactor Program have been directed toward (1) further measurements and predictions of reactor product migration at Oklo, (2) uraninite solubility studies, (3) radiogenic equilibria studies of natural Pu, Ra, and Th in U ores, (4) search for evidence of other natural fission reactors, and (5) supportive analytical measurements and procedures development.
Date:
November 1, 1977
Creator:
Apt, K.E. (ed.)
System:
The UNT Digital Library
Ocean thermal difference power plant turbine design
None
Date:
November 1, 1973
Creator:
Ambs, L. L. & Marshall, J.
System:
The UNT Digital Library
Preliminary design of a magnetohydrodynamic (MHD) channel for the U. S. S. R. U-25 facility. Final report
None
Date:
November 1, 1974
Creator:
Brogan, T R; Aframe, A M & Hill, J
System:
The UNT Digital Library
Multiperipheral ring dynamics and a definition of the complete twisted Reggeon loop. [Diagonalization, naturality, threshold behavior, Regge cuts, complex helicity]
The t less than 0 multiperipheral formalism of Ciafaloni, DeTar, Misheloff, Mueller, Muzinich and Yesian is reviewed, extended, and applied to the ordered S-matrix whose ring amplitudes comprise the zeroth level of the topological expansion. Toller M-function notation is used throughout. The bootstrap and cylinder problems are formulated in terms of a well defined helicity pole propagator; a definition of the complete twisted Reggeon loop, which appears in the one-twist term of the cylinder, is given as a helicity pole expansion. Some consideration is given to the following subjects: diagonalization, naturality, threshold behavior, Regge cuts, and complex helicity.
Date:
November 1, 1977
Creator:
Lucht, P.H.
System:
The UNT Digital Library
PROCESSES FOR RECOVERY OF URANIUM AND THORIUM FROM GRAPHITE-BASE FUEL ELEMENTS. PART II
Laboratory-scale tests on methods for recovering uranium and thorium from graphite-base reactor fuel elements are reported. The 90% HNO/sub 3/ process, which involves simultaneous disintegration and leaching in 21 M HNO/sub 3/, is applicable to all fuel elenments which do not contain coated fuel particles. Leaching of irradiated (0.001% burnup) fuels containing 3 and 12% uranlum recovered approximates 99.3 and 99.9%, respectively, of the uranium in two 4-hr leaches with boiling acid. The graphite residue retained > 50% of the long-lived fission products. Three successive leaches of fuel containing uranium and thorium recovered approximates 99% of both elements. Uranium recoveries by combustion in oxygen followed by dissolution of the ash hn nitric acid or fluorlde-catalyzed nitric acid are quantitative only when the fuel is not coated, does not contain Al/sub 2/O/sub 3/-coated fuel particles, and is free from impurities such as iron. During combustion up to 95% of the Ru-106 was volatilized from irradiated specimens. Recoveries, by leaching with 70% HNO/sub 3/, from fuel specimens containing Al/sub 2/O/sub 3/-coated fuel particles were greater than 99% when the specimens were ground finer than 200 mesh to ensure crushing of the fuel particles. (auth)
Date:
November 30, 1961
Creator:
Ferris, L.M.; Kibbey, A.H. & Bradley, M.J.
System:
The UNT Digital Library
Evaluation of Wire Scanner for SM-1
Preliminary design concepts are presented for a wire scanner for experimentally evaluating spatial variations of neutron flux in the SM-l reactor core. Results of a literature search and determination of optimum criteria for flux mapping the core in minimum time dictated requirements for design concepts and specifications. The utility of both manually instrumented and automatically instrumented wire scanners was analyzed with respect to rapidity of measurement, selectivity of detector location, cost, value of data, plant downtime, and additional factors. (auth)
Date:
November 22, 1961
Creator:
Kemp, S. N.
System:
The UNT Digital Library
CONCEPTUAL DESIGN AND ECONOMIC EVALUATION OF A STEAM-COOLED FAST BREEDER REACTOR
A conceptual design and economic evaluation of 300 and 40 MW/.sub e/ steam-cooled fast breeder reactor power plants were performed. A reactor core composed of U-Pu oxide rod-type fuel elements clad with Inconel-X and surrounded by a blanket of depleted UO/sub 2/ fuel was studied in some detail. Reactor breeding ratios of from 1.27 to 1.5 and overall system doubling times of from 20 to 30 years are achievable. For the near term (1967) 300 MW/sub e/ plant, an energy cost of 7.6 mills/kwh is estimated, based on AEC ground rules for privately financed plants and utilities. This cost may go down to 5.7 mills/kwh by 1975. For the 40 MW/sub e/ plant corresponding energy costs are 19.5 and 13.7 mills/kwh, r -spectively. The R&D program required for this reactor concept is estimated at million with an additional million for improvements leading to the 1975 reactor. Investigation of the operational and safety aspects of the reactor indicated that satisfactory procedures can be used for startup, shutdown, and emergency cooling of the reactor. An increase in reactivity upon flooding can be prevented by incorprating small amounts of high resonance absorption material in the core. Preliminary calculations indicate a substantial increase in …
Date:
November 15, 1961
Creator:
Sofer, G.; Hankel, R.; Goldstein, L. & Birman, G.
System:
The UNT Digital Library