“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.
Edwards, D. R.
Hale, Barbara N.
Nuclear Engineering and Radiation Science
M.S. in Nuclear Engineering
University of Missouri--Rolla
viii, 63 pages
© 2000 Micheal Addison Smith, All rights reserved.
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Smith, Micheal Addison, "Implementation of the finite element method in a nodal transport program to allow for heterogeneous geometries" (2000). Masters Theses. 1979.
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