Monte Carlo Studies of Gamma-ray and Neutron Transport in Infinite Homogeneous Media
Author : Theodore E. Fessler
Publisher :
Page : 54 pages
File Size : 12,81 MB
Release : 1961
Category : Nuclear physics
ISBN :
Author : Theodore E. Fessler
Publisher :
Page : 54 pages
File Size : 12,81 MB
Release : 1961
Category : Nuclear physics
ISBN :
Author : Theodore E. Fessler
Publisher :
Page : 1 pages
File Size : 10,34 MB
Release : 1961
Category :
ISBN :
Two point-source, infinite-medium Monte Carlo codes were written for the IBM 704 computer. The codes simulate respectively gamma-ray and neutron transport from a monoenergetic source. A detailed description, including importance sampling methods, is given. Results showed good agreement with moments-method calculations for the same geometry. Calculations for 6-Mev gamma rays in tin provide data on the contribution of annihilation radiation to both the buildup factors and energy spectra. Calculations for 1-Mev gamma rays in water are also presented. The results of calculations for 6-Mev source neutrons in water show a peak in the energy spectrum which is found to be due to single scattering of source particles from oxygen. (Author).
Author :
Publisher :
Page : 530 pages
File Size : 29,12 MB
Release : 1962
Category :
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Author : Millard L. Wohl
Publisher :
Page : 24 pages
File Size : 24,92 MB
Release : 1962
Category : Propulsion systems
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Author : United States. National Aeronautics and Space Administration
Publisher :
Page : 448 pages
File Size : 19,62 MB
Release : 1960
Category : Aeronautics
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Author :
Publisher :
Page : 44 pages
File Size : 28,92 MB
Release : 1964
Category : Physics
ISBN :
Author : Andreas Kling
Publisher : Springer Science & Business Media
Page : 1200 pages
File Size : 20,11 MB
Release : 2014-02-22
Category : Science
ISBN : 3642182119
This book focuses on the state of the art of Monte Carlo methods in radiation physics and particle transport simulation and applications. Special attention is paid to algorithm development for modeling, and the analysis of experiments and measurements in a variety of fields.
Author :
Publisher :
Page : pages
File Size : 11,67 MB
Release : 2015
Category :
ISBN :
The time-dependent behavior of the energy spectrum in neutron transport was investigated with a formulation, based on continuous-time Markov processes, for computing [alpha] eigenvalues and eigenvectors in an infinite medium. In this study, a research Monte Carlo code called "TORTE" (To Obtain Real Time Eigenvalues) was created and used to estimate elements of a transition rate matrix. TORTE is capable of using both multigroup and continuous-energy nuclear data, and verification was performed. Eigenvalue spectra for infinite homogeneous mixtures were obtained, and an eigenfunction expansion was used to investigate transient behavior of the neutron energy spectrum.
Author : Defense Documentation Center (U.S.)
Publisher :
Page : 464 pages
File Size : 37,94 MB
Release : 1962
Category : Technology
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Author :
Publisher :
Page : 516 pages
File Size : 44,67 MB
Release : 1973
Category : Nuclear energy
ISBN :