Mixed energy reactor simulations using the discrete generalized multigroup method
Name
leizhu_NSEpaper.pdf
Description
Accepted version
Size
575.95 KB
Format
Adobe PDF
Checksum (MD5)
a25b25ef654adfaf830c1a9545b2b5ab
Author(s)
Forget, Benoit Robert Yves
Zhu, Lei
Date Issued
2010
Journal
International Conference on the Physics of Reactors 2010
Publisher
Curran Associates
Citation
Forget, Benoit and Lei Zhu. "Mixed energy reactor simulations using the discrete generalized multigroup method." International Conference on the Physics of Reactors 2010, Pittsburgh, Pennsylvania, USA, Curran Associates, 2010. © 2010 Curran Associates
Version
Author's final manuscript
Abstract
An innovative approach to mixed energy simulations was proposed. This approach is based on the generalized multigroup theory using discrete orthogonal polynomials. The discrete expansion provides a link between a coarse group structure and a fine group structure, thus allowing for coarse group calculations to provide an approximation of the within group spectral information. A mixed energy scheme can be adapted from this work by which certain regions are based on the coarse group energy structure which is a subset of a finer group structure that can be used in certain regions. The higher moment equations of the coarse group calculations are used to provide fine group spectral information at the boundaries of the regions. Simple 1-D diffusion results indicate that fine group flux can be reproduced accurately in a mixed energy solution and that significant improvement of the eigenvalue estimate can be obtained when comparing with common coarse and fine multigroup solutions.
MIT Department
Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
Terms of Use
Creative Commons Attribution-Noncommercial-Share Alike
Persistent DSpace Link
DOI of Published Version
http://toc.proceedings.com/09515webtoc.pdf
