Title:
Multilevel acceleration of neutron transport calculations

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dc.contributor.advisor Stacey, Weston M.
dc.contributor.advisor de Oliveira, Cassiano R. E.
dc.contributor.author Marquez Damian, Jose Ignacio en_US
dc.contributor.committeeMember Hertel, Nolan
dc.contributor.committeeMember van Rooijen, Wilfred F.G.
dc.contributor.department Nuclear and Radiological Engineering en_US
dc.date.accessioned 2008-02-07T18:13:47Z
dc.date.available 2008-02-07T18:13:47Z
dc.date.issued 2007-08-24 en_US
dc.description.abstract Nuclear reactor design requires the calculation of integral core parameters and power and radiation profiles. These physical parameters are obtained by the solution of the linear neutron transport equation over the geometry of the reactor. In order to represent the fine structure of the nuclear core a very small geometrical mesh size should be used, but the computational capacity available these days is still not enough to solve these transport problems in the time range (hours-days) that would make the method useful as a design tool. This problem is traditionally solved by the solution of simple, smaller problems in specific parts of the core and then use a procedure known as homogenization to create average material properties and solve the full problem with a wider mesh size. The iterative multi-level solution procedure is inspired in this multi-stage approach, solving the problem at fuel-pin (cell) level, fuel assembly and nodal levels. The nested geometrical structure of the finite element representation of a reactor can be used to create a set of restriction/prolongation operators to connect the solution in the different levels. The procedure is to iterate between the levels, solving for the error in the coarse level using as source the restricted residual of the solution in the finer level. This way, the complete problem is only solved in the coarsest level and in the other levels only a pair of restriction/interpolation operations and a relaxation is required. In this work, a multigrid solver is developed for the in-moment equation of the spherical harmonics, finite element formulation of the second order transport equation. This solver is implemented as a subroutine in the code EVENT. Numerical tests are provided as a standalone diffusion solver and as part of a block Jacobi transport solver. en_US
dc.description.degree M.S. en_US
dc.identifier.uri http://hdl.handle.net/1853/19731
dc.publisher Georgia Institute of Technology en_US
dc.subject Multilevel en_US
dc.subject Multigrid en_US
dc.subject Transport en_US
dc.subject Reactor en_US
dc.subject Gauss en_US
dc.subject Seidel en_US
dc.subject Jacobi en_US
dc.subject Interpolation en_US
dc.subject Restriction en_US
dc.subject Spherical harmonics en_US
dc.subject Finite element en_US
dc.subject Finite elements en_US
dc.subject Event en_US
dc.subject.lcsh Nuclear reactors
dc.subject.lcsh Multigrid methods (Numerical analysis)
dc.subject.lcsh Spherical harmonics
dc.subject.lcsh Transport theory
dc.subject.lcsh Radiative transfer
dc.title Multilevel acceleration of neutron transport calculations en_US
dc.type Text
dc.type.genre Thesis
dspace.entity.type Publication
local.contributor.advisor Stacey, Weston M.
local.contributor.corporatename George W. Woodruff School of Mechanical Engineering
local.contributor.corporatename College of Engineering
relation.isAdvisorOfPublication c0f53c49-e84d-46a7-b831-23770e787081
relation.isOrgUnitOfPublication c01ff908-c25f-439b-bf10-a074ed886bb7
relation.isOrgUnitOfPublication 7c022d60-21d5-497c-b552-95e489a06569
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