Masters Theses


“The focus of this thesis is the implementation of the finite element approximation within an existing nodal transport code. The nodal transport method allows the geometry of the reactor to be split up into regular bodies, such as boxes and hexagonal prisms, called nodes. Previous to this work, a single set of cross sections was obtained for each node by homogenizing the heterogeneous structure such that the reaction rates within the node were preserved. Unfortunately, the dependence of the flux on the heterogeneous structure was lost and the heterogeneous flux could only be approximated. For issues such as fuel cladding integrity, the accuracy of the heterogeneous flux is very important and any improvements in the calculated flux pose a significant advantage. The use of the finite element structure within the nodal transport method allows for the explicit treatment of the heterogeneous structure and thus no homogenization is required.

It will be shown that with the new method the heterogeneous flux can be accurately calculated, but it comes at some expense because of the high order angular approximation required. It is believed, however, that with the recent improvements in computer technology and the advantages that the nodal method offers, this new application will prove a viable method to solve reactor core problems”--Abstract, page iii.


Tsoulfanidis, Nicholas

Committee Member(s)

Edwards, D. R.
Hale, Barbara N.


Nuclear Engineering and Radiation Science

Degree Name

M.S. in Nuclear Engineering


The author thanks the U.S. Department of Energy for their support under Contract No. W-31-109- ENG-38 and Contract No. DE-FG07-98ID13632, which funded this project.


University of Missouri--Rolla

Publication Date

Fall 2000


viii, 63 pages

Note about bibliography

Includes bibliographical references (pages 61-62).


© 2000 Micheal Addison Smith, All rights reserved.

Document Type

Thesis - Restricted Access

File Type




Thesis Number

T 7832

Print OCLC #


Link to Catalog Record

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