Air and Concrete Scattering of Neutrons - Monte Carlo Calculations PDF Download
Are you looking for read ebook online? Search for your book and save it on your Kindle device, PC, phones or tablets. Download Air and Concrete Scattering of Neutrons - Monte Carlo Calculations PDF full book. Access full book title Air and Concrete Scattering of Neutrons - Monte Carlo Calculations by M. B. Wells. Download full books in PDF and EPUB format.
Author: M. B. Wells Publisher: ISBN: Category : Languages : en Pages : 42
Book Description
This report presents results from Monte Carlo calculations of the angular distribution of neutrons scattered from air and concrete. The Monte Carlo method was used to evaluate the integrals that represent the contribution to the total scattered flux from the first five orders of scattering. The scattered neutron flux at various separation distances was computed for a 3.25 Mev point monodirectional source located at a height of 12.5 feet above the surface of a concrete slab. Differential scattering cross sections based on a complex square well model and differential scattering cross sections assuming isotropic scattering in the center of mass system were used in the Monte Carlo calculations. The method used in computing the variance of the scattered flux is outlined. The standard deviation computed was found to be generally not more than 10% of the scattered flux. This report supplements the information presented in Convair-Fort Worth report FZK-9-120A.
Author: M. B. Wells Publisher: ISBN: Category : Languages : en Pages : 42
Book Description
This report presents results from Monte Carlo calculations of the angular distribution of neutrons scattered from air and concrete. The Monte Carlo method was used to evaluate the integrals that represent the contribution to the total scattered flux from the first five orders of scattering. The scattered neutron flux at various separation distances was computed for a 3.25 Mev point monodirectional source located at a height of 12.5 feet above the surface of a concrete slab. Differential scattering cross sections based on a complex square well model and differential scattering cross sections assuming isotropic scattering in the center of mass system were used in the Monte Carlo calculations. The method used in computing the variance of the scattered flux is outlined. The standard deviation computed was found to be generally not more than 10% of the scattered flux. This report supplements the information presented in Convair-Fort Worth report FZK-9-120A.
Author: I. Lux Publisher: CRC Press ISBN: 1351083287 Category : Science Languages : en Pages : 530
Book Description
With this book we try to reach several more-or-less unattainable goals namely: To compromise in a single book all the most important achievements of Monte Carlo calculations for solving neutron and photon transport problems. To present a book which discusses the same topics in the three levels known from the literature and gives us useful information for both beginners and experienced readers. It lists both well-established old techniques and also newest findings.
Author: D. M. Wheeler Publisher: ISBN: Category : Nuclear reactors Languages : en Pages : 242
Book Description
Experimental data were obtained on neutron and gamma-ray attenuation and on neutron activation for representative field materials and on air scattering of radiation. Field materials tested were dry sand, wet sand, clay, limestone, water, a soil mixture, and pine wood. Results of the experiments showed the following: of the materials tested a given thickness afforded more fast-neutron attenuation than gamma-ray attenuation. Secondary-gamma-ray production in expedient materials is an important consideration dependent on the water (hydrogen) content in the material.
Author: F. H. Clark Publisher: ISBN: Category : Languages : en Pages : 24
Book Description
The 05R Monte Carlo code (See ORNL-3622, NASA N65-17892) was adapted to calculate fast-neutron doses within and outside of concrete slab shields. Such calculations were performed for a variety of shield thicknesses (0 to 180 cm) and for various monoenergetic sources from 0.7 to 14 MeV. The concrete chosen is ordinary concrete with approximately 6% water content. Results are plotted as tissue kerma versus penetration distance for each source energy. The source is in each case a broad normally incident beam. (Author).
Author: M. B. Wells
Author: M. B. Wells
Author: F. L. Keller
Author: I. Lux
Author: Wendell De Marcus
Author: 
Author: C. D. Zerby
Author: D. M. Wheeler
Author: M. Lewis Nelson
Author: F. H. Clark
Author: