The Green's dyadic method for the analytic solution of multigroup neutron transport boundary value problems

An extension of the Green's function method is developed for the exact solution of the multigroup neutron transport equation. The method is based on the treatment of the steady-state, plane geometry multigroup equations for general anisotropic scattering in a homogenous medium. The problem of a system of N coupled integrodifferential equations is reduced to the evaluation of an NXN dyadic by the Green's dyadic method. Each dyadic element represents neutron scatterring from one energy group to another.

Name thesis:degree_name

Ph.D.

Level thesis:degree_level

Dissertation

Discipline thesis:degree_discipline

Nuclear, Plasma, and Radiological Engineering

Grantor

University of Illinois at Urbana-Champaign

Year dc:date

2011

Author dc:creator

• Atalay, Mehmet Akif

Contributors dc:contributor

• Axford, Roy A.

• Engineering, Nuclear

Statement dc:rights

• Copyright 1990 Atalay, Mehmet Akif

Language dc:language

eng

Identifier

AAI9114167
(UMI)AAI9114167

OAI identifier oai:identifier

oai:www.ideals.illinois.edu:2142/22694