An IBM 704 Program for the Solution of the Neutron Transport Equation in Fifty Concentric Alluli by the Weil Method, Program I2
Author: Robert R. McCready
Publisher:
Published: 1959
Total Pages: 68
ISBN-13:
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Author: Robert R. McCready
Publisher:
Published: 1959
Total Pages: 68
ISBN-13:
DOWNLOAD EBOOKAuthor:
Publisher:
Published: 1960
Total Pages:
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DOWNLOAD EBOOKAuthor: Richard R. Haefner
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Published: 1959
Total Pages: 68
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DOWNLOAD EBOOKAuthor: E. H. Auerbach
Publisher:
Published: 1959
Total Pages: 84
ISBN-13:
DOWNLOAD EBOOKUFO is a code for the approximate solution of the three-dimensional, few-group, neutron diffusion equation on the IBM 704. Both the theory and operation of the program are discussed.
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Published: 1959
Total Pages:
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DOWNLOAD EBOOKProgram George is an IBM 704 ccde that combines standard ANPD reactor analysis methcds for computing multiplication constant and spatial distribution of flux and power, as well as other nuclear parameters, in aircraft (heterogeneous) reactors. The elapsed time and the chance for human error between initial input and final output are greatly reduced in Program George. A matched set of reflector savings for a reflected, cylindrical core, which was formerly obtained by hand, is now computed by the program. In the C/sub 2/ pcrtion of Program George, the ccde computes the neutron slowingdown density and flux at 19 lethargy levels plus a thermal group in bare, homogeneous compositions with normal mode, ene ngy-dependent bucklings. The diffusion coefficient contains a transport correction as well as a Behrens correction for heterogeneous structure. Flux-depression factors at thermal and two epithermal levels are computed in annular, cylindrical geometry by one-energy, P/sub 3/ transport theory approximation in the I/sub 2/ pontion of the program, or they may be given as input. Flux weighting of various cross sections, transmission factors, and other parameters are computed in a multigroup representation. Two-energy-group constants from the regional compositions are supplied in the F/sub 2/ portion of the program, in which a two-energy group, one-space-dimensional, multiregion diffusion calculation yields multiplication constant, normalized fission density, fast flux, and slow flux in each onedimensional reactor pontrayed. If a reactivity match is requested, the reflector savings of the specified compositions are adjusted until the multiplication constant i n the radial F/sub 2/, longitudinal F/sub 2/, and the reference bare equivalent core of a cylindrical reflected reactor converge to the same value. (auth).
Author: Henry Weinberg
Publisher:
Published: 1966
Total Pages: 38
ISBN-13:
DOWNLOAD EBOOKThe Circuit Analysis Program was prepared for the IBM 704 computer and is written in the FORTRAN and SAP-FORTRAN languages. In this report, the program is used to analyze R-L-C (resistance, inductance, and capacitance) electric networks and, once the proper analogies are made, resolve problems relative to obtaining eigenvalues and roots of polynomials and solving systems of general linear equations. Examples of some of the above problems are provided. The total number of equations for each problem cannot exceed 30. Accuracy of the solution is improved by using two 36 binary bit words to represent each number, but execution time is sacrificed. The requestor controls the format used to read the equation parameters; thereby, the flexibility of the program is increased, and the possibility of transcribing errors is reduced. Three methods for evaluating a determinant with quadratic elements were tried, and it was decided that the method of 'false position' is the most effective because of its advantageous storage and time requirements and greater accuracy. (Author).