Development of a polynomial nodal model to the multigroup transport equation in one dimension

Thumbnail Image
Date
1986
Authors
Feiz, Masoud
Major Professor
Advisor
Committee Member
Journal Title
Journal ISSN
Volume Title
Publisher
Altmetrics
Authors
Research Projects
Organizational Units
Journal Issue
Is Version Of
Versions
Series
Department
Nuclear Engineering
Abstract

A polynomial nodal model which uses Legendre polynomial expansions was developed for the multigroup transport equation in one dimension. The development depends upon the least squares minimization of the residuals using the approximate functions over the node. Analytical expressions were developed for the polynomial coefficients. The odd moments of the angular neutron flux over the half ranges were used at the internal interfaces, and the Marshak boundary condition was used at the external boundaries. Sample problems with fine mesh finite difference solutions of the diffusion and transport equations were used for comparison with the model.

Comments
Description
Keywords
Citation
Source
Subject Categories
Copyright
Wed Jan 01 00:00:00 UTC 1986