Multilevel acceleration of neutron transport calculations

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...

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Main Author: Marquez Damian, Jose Ignacio
Published: Georgia Institute of Technology 2008
Subjects:
Online Access:http://hdl.handle.net/1853/19731
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spelling ndltd-GATECH-oai-smartech.gatech.edu-1853-197312013-01-07T20:23:55ZMultilevel acceleration of neutron transport calculationsMarquez Damian, Jose IgnacioMultilevelMultigridTransportReactorGaussSeidelJacobiInterpolationRestrictionSpherical harmonicsFinite elementFinite elementsEventNuclear reactorsMultigrid methods (Numerical analysis)Spherical harmonicsTransport theoryRadiative transferNuclear 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.Georgia Institute of Technology2008-02-07T18:13:47Z2008-02-07T18:13:47Z2007-08-24Thesishttp://hdl.handle.net/1853/19731
collection NDLTD
sources NDLTD
topic Multilevel
Multigrid
Transport
Reactor
Gauss
Seidel
Jacobi
Interpolation
Restriction
Spherical harmonics
Finite element
Finite elements
Event
Nuclear reactors
Multigrid methods (Numerical analysis)
Spherical harmonics
Transport theory
Radiative transfer
spellingShingle Multilevel
Multigrid
Transport
Reactor
Gauss
Seidel
Jacobi
Interpolation
Restriction
Spherical harmonics
Finite element
Finite elements
Event
Nuclear reactors
Multigrid methods (Numerical analysis)
Spherical harmonics
Transport theory
Radiative transfer
Marquez Damian, Jose Ignacio
Multilevel acceleration of neutron transport calculations
description 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.
author Marquez Damian, Jose Ignacio
author_facet Marquez Damian, Jose Ignacio
author_sort Marquez Damian, Jose Ignacio
title Multilevel acceleration of neutron transport calculations
title_short Multilevel acceleration of neutron transport calculations
title_full Multilevel acceleration of neutron transport calculations
title_fullStr Multilevel acceleration of neutron transport calculations
title_full_unstemmed Multilevel acceleration of neutron transport calculations
title_sort multilevel acceleration of neutron transport calculations
publisher Georgia Institute of Technology
publishDate 2008
url http://hdl.handle.net/1853/19731
work_keys_str_mv AT marquezdamianjoseignacio multilevelaccelerationofneutrontransportcalculations
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