Published 1995 | Version v1
Journal article

Angular Green's function flux in an infinite medium with anisotropic scattering

  • 1. Univ. of Arizona, Tucson, AZ (United States)

Description

In elementary texts on transport theory, the first problem usually demonstrated is the Green's function for the one-group transport equation in an infinite medium. In the following analysis, the angular Green's function in an infinite medium with anisotropic scattering is obtained via Fourier transform methods. The inversion is then performed numerically. The angular Green's function solution with anisotropic scattering can be obtained numerically with minimal input indicating only the desired relative error, the coefficients of the scattering kernel, and the spatial edit points. In this paper, modern numerical methods are for the first time applied to this basic transport problem

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
73
Journal Page Range
p. 188-189.
ISSN
0003-018X
CODEN
TANSAO

Conference

Title
Winter meeting of the American Nuclear Society (ANS).
Dates
29 Oct - 1 Nov 1995.
Place
San Francisco, CA (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
28020262
Subject category
S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CALCULATION METHODS; GREEN FUNCTION; NEUTRON TRANSPORT; NUMERICAL SOLUTION; TRANSPORT THEORY
Descriptors DEC
FUNCTIONS; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT

Optional Information

Secondary number(s)
CONF-951006--.