Monte Carlo Studies of Gamma-ray and Neutron Transport in Infinite Homogeneous Media
Title | Monte Carlo Studies of Gamma-ray and Neutron Transport in Infinite Homogeneous Media PDF eBook |
Author | Theodore E. Fessler |
Publisher | |
Pages | 54 |
Release | 1961 |
Genre | Nuclear physics |
ISBN |
Monte Carlo Studies of Gamma-ray and Neutron Transport in Infinite Homogeneous Media
Title | Monte Carlo Studies of Gamma-ray and Neutron Transport in Infinite Homogeneous Media PDF eBook |
Author | Theodore E. Fessler |
Publisher | |
Pages | 1 |
Release | 1961 |
Genre | |
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).
NASA Technical Note
Title | NASA Technical Note PDF eBook |
Author | |
Publisher | |
Pages | 530 |
Release | 1962 |
Genre | |
ISBN |
Monte Carlo Calculations of Neutron Number Sprectra and Buildup Factors in Infinite Conical Configurations
Title | Monte Carlo Calculations of Neutron Number Sprectra and Buildup Factors in Infinite Conical Configurations PDF eBook |
Author | Millard L. Wohl |
Publisher | |
Pages | 24 |
Release | 1962 |
Genre | Propulsion systems |
ISBN |
Index of NASA Technical Publications
Title | Index of NASA Technical Publications PDF eBook |
Author | United States. National Aeronautics and Space Administration |
Publisher | |
Pages | 448 |
Release | 1960 |
Genre | Aeronautics |
ISBN |
Calculating Infinite-medium [alpha]-eigenvalue Spectra with Monte Carlo Using a Transition Rate Matrix Method
Title | Calculating Infinite-medium [alpha]-eigenvalue Spectra with Monte Carlo Using a Transition Rate Matrix Method PDF eBook |
Author | |
Publisher | |
Pages | |
Release | 2015 |
Genre | |
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.
NBS Monograph
Title | NBS Monograph PDF eBook |
Author | |
Publisher | |
Pages | 44 |
Release | 1964 |
Genre | Physics |
ISBN |