Three-dimensional nodal neutron transport program with the ability to handle spatial heterogeneities

Author

Micheal Addison Smith

Abstract

"In this dissertation a finite element spatial approximation has been implemented into a nodal transport framework. In general, a nodal approach splits up the geometry for a neutron transport problem into regular bodies, such as boxes and hexagonal prisms, called nodes, and couples the nodes together at the nodal interfaces. The use of the finite element structure within the nodal geometry allows for the explicit treatment of the heterogeneous material structure within each node. The theory behind this method is based upon a Rayleigh-Ritz variational functional obtained for the even-parity form of the multigroup Boltzmann neutron transport equation. The new approach eliminates many of the problems associated with previous nodal approaches in which homogenization procedures had been employed; it can treat a variety of spatial geometries using finite element meshes of mixed origin (triangles, boxes, polygons, etc.) combined with PN and SPN angular approximations.

With the new method, it is shown that the heterogeneous flux can be accurately calculated, but it is done at some computational expense because of the high order angular approximation required. It is believed that with the recent improvements in computer technology and the advantages that the nodal method offers, this new method will prove to be a valuable tool to solve reactor core problems"-- Abstract, p. iii

Advisor(s)

Tsoulfanidis, Nicholas

Committee Member(s)

Edwards, D. R.
Hale, Barbara N., 1938-2024
Tokuhiro, Akira
Lewis, Elmer E.

Department(s)

Nuclear Engineering and Radiation Science

Degree Name

Ph. D. in Nuclear Engineering

Comments

Accompanying CD-ROM, available at Missouri S&T Library, contains Appendices B-K.
System requirements for accompanying computer disc: Ability to read files in MathCad, Microsoft Powerpoint, Microsoft Word and 3-D.

Publisher

University of Missouri--Rolla

Publication Date

Fall 2001

Pagination

xii, 164 pages; CD-ROM

Note about bibliography

Includes bibliographical references (pages 158-163).

Rights

© 2001 Micheal Addison Smith, All rights reserved.

Document Type

Dissertation - Restricted Access

File Type

text

Language

English

Thesis Number

T 7963

Print OCLC #

49074761

Recommended Citation

Smith, Micheal Addison, "Three-dimensional nodal neutron transport program with the ability to handle spatial heterogeneities" (2001). Doctoral Dissertations. 1405.
https://scholarsmine.mst.edu/doctoral_dissertations/1405