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

Simple item page
dc.contributor.author Feiz, Masoud
dc.contributor.department Nuclear Engineering
dc.date 2018-08-15T06:16:11.000
dc.date.accessioned 2020-07-02T06:05:39Z
dc.date.available 2020-07-02T06:05:39Z
dc.date.copyright Wed Jan 01 00:00:00 UTC 1986
dc.date.issued 1986
dc.description.abstract <p>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.</p>
dc.format.mimetype application/pdf
dc.identifier archive/lib.dr.iastate.edu/rtd/8246/
dc.identifier.articleid 9245
dc.identifier.contextkey 6331077
dc.identifier.doi https://doi.org/10.31274/rtd-180813-6886
dc.identifier.s3bucket isulib-bepress-aws-west
dc.identifier.submissionpath rtd/8246
dc.identifier.uri https://dr.lib.iastate.edu/handle/20.500.12876/81213
dc.language.iso en
dc.source.bitstream archive/lib.dr.iastate.edu/rtd/8246/r_8703705.pdf|||Sat Jan 15 02:08:41 UTC 2022
dc.subject.disciplines Nuclear Engineering
dc.subject.keywords Nuclear engineering
dc.title Development of a polynomial nodal model to the multigroup transport equation in one dimension
dc.type article
dc.type.genre dissertation
dspace.entity.type Publication
thesis.degree.level dissertation
thesis.degree.name Doctor of Philosophy
File
Original bundle
Now showing 1 - 1 of 1
Name:
r_8703705.pdf
Size:
860.59 KB
Format:
Adobe Portable Document Format
Description:
Download
Collections
Theses and Dissertations