Title:
Flux-limited Diffusion Coefficient Applied to Reactor Analysis

dc.contributor.advisor Rahnema, Farzad
dc.contributor.author Keller, Steven Ede en_US
dc.contributor.committeeMember Daniel W. Tedder
dc.contributor.committeeMember Hertel, Nolan E.
dc.contributor.committeeMember Thomas D. Morley
dc.contributor.committeeMember Stacey, Weston M. , Jr.
dc.contributor.department Nuclear Engineering en_US
dc.date.accessioned 2007-08-16T17:36:57Z
dc.date.available 2007-08-16T17:36:57Z
dc.date.issued 2007-07-09 en_US
dc.description.abstract A new definition of the diffusion coefficient for use in reactor physics calculations is evaluated in this thesis. It is based on naturally flux-limited diffusion theory (FDT), sometimes referred to as Levermore-Pomraning diffusion theory. Another diffusion coefficient more loosely based on FDT is also evaluated in this thesis. Flux-limited diffusion theory adheres to the physical principle of flux-limiting, which is that the magnitude of neutron current is not allowed to exceed the scalar flux. Because the diffusion coefficients currently used in the nuclear industry are not flux-limited they may violate this principle in regions of large spatial gradients, and because they encompass other assumptions, they are only accurate when used in the types of calculations for which they were intended. The evaluations were performed using fine-mesh diffusion theory. They are in one spatial dimension and in 47, 4, and 2 energy groups, and were compared against a transport theory benchmark using equivalent energy structures and spatial discretization. The results show that the flux-limited diffusion coefficient (FD) outperforms the standard diffusion coefficient in calculations of single assemblies with vacuum boundaries, according to flux- and eigenvalue-errors. In single assemblies with reflective boundary conditions, the FD yielded smaller improvements, and tended to improve only the fast-group results. The results also computationally confirm that the FD adheres to flux-limiting, while the standard diffusion coefficient does not. en_US
dc.description.degree Ph.D. en_US
dc.identifier.uri http://hdl.handle.net/1853/16126
dc.publisher Georgia Institute of Technology en_US
dc.subject Transport cross section en_US
dc.subject Reactor physics en_US
dc.title Flux-limited Diffusion Coefficient Applied to Reactor Analysis en_US
dc.type Text
dc.type.genre Dissertation
dspace.entity.type Publication
local.contributor.advisor Rahnema, Farzad
local.contributor.corporatename George W. Woodruff School of Mechanical Engineering
local.contributor.corporatename College of Engineering
relation.isAdvisorOfPublication 1d96b222-d2f0-46d1-a0c7-4d1f9254dfab
relation.isOrgUnitOfPublication c01ff908-c25f-439b-bf10-a074ed886bb7
relation.isOrgUnitOfPublication 7c022d60-21d5-497c-b552-95e489a06569
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