
Accession Number : AD0480699
Title : AFWLATAC JOINT SHIELDING PROGRAM. INVESTIGATION OF ANALYTICAL METHODS, SOLUTION SENSITIVITY, AND STRUCTURAL SCATTERING IN NEUTRON TRANSPORT.
Descriptive Note : Technical rept. 1 Oct 6430 Sep 65,
Corporate Author : GENERAL DYNAMICS CORP FORT WORTH TX
Personal Author(s) : Norwood, J. M. ; Jones, E. E. ; Goodwin, D. A. ; Kleinjan, P. L.
Report Date : MAR 1966
Pagination or Media Count : 124
Abstract : A limited investigation has been made of the effect of crosssection measurement error and of crosssection approximation upon the transportequation solution at deep penetration. The most serious error in deep penetration calculations appears to arise from inadequate treatment of anisotropic scattering; a P1 scattering kernel is not adequate. Other aspects of the problem are included in the study. It is recommended that calculations be made to deep penetration with transport codes capable of handling anisotropic scattering. An analytical approach to the solution of the multigroup formulation of the transport equation has been studied and the method yields the correct functional form of the vector flux in terms of the penetration distance and neutron directions of motion. Complete solution requires the inversion of large matrices. A method of inclusion of thetadependence in the multigroup transport equation applicable to slab geometry has been investigated. The method should be practical for crewcompartment shielding calculations. The scattering of fast neutrons from structures was subjected to a limited investigation by means of Monte Carlo methods, and approximate analytical formulas applicable to materials with strongly peaked forward scattering were derived. (Author)
Descriptors : (*NUCLEAR PARTICLES, SHIELDING), TRANSPORT PROPERTIES, THEORY, NEUTRON SCATTERING, NEUTRON CROSS SECTIONS, APPROXIMATION(MATHEMATICS), MONTE CARLO METHOD, PENETRATION, ATOMIC PROPERTIES, HYDRIDES, LITHIUM COMPOUNDS, AIRCRAFT CABINS, COCKPITS, THERMAL RADIATION, POLYETHYLENE PLASTICS, IRON, FAST NEUTRONS, THERMAL NEUTRONS, NEUTRON FLUX, EXPONENTIAL FUNCTIONS.
Subject Categories : Nuclear Physics & Elementary Particle Physics
Distribution Statement : APPROVED FOR PUBLIC RELEASE