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dc.contributor.advisorRagusa, Jean C.
dc.creatorSternat, Matthew Ryan
dc.date.accessioned2011-02-22T22:23:40Z
dc.date.accessioned2011-02-22T23:44:55Z
dc.date.available2011-02-22T22:23:40Z
dc.date.available2011-02-22T23:44:55Z
dc.date.created2009-12
dc.date.issued2011-02-22
dc.date.submittedDecember 2009
dc.identifier.urihttp://hdl.handle.net/1969.1/ETD-TAMU-2009-12-7311
dc.description.abstractThe problem of inferring or reconstructing the material properties (cross sections) of a domain through noninvasive techniques, methods using only input and output at the domain boundary, is attempted using the governing laws of neutron diffusion theory as an optimization constraint. A standard Lagrangian was formed consisting of the objective function and the constraints to satisfy, which was minimized through optimization using a line search method. The chosen line search method was Newton's method with the Armijo algorithm applied for step length control. A Gaussian elimination procedure was applied to form the Schur complement of the system, which resulted in greater computational efficiency. In the one energy group and multi-group models, the limits of parameter reconstruction with respect to maximum reconstruction depth, resolution, and number of experiments were established. The maximum reconstruction depth for one-group absorption cross section or multi-group removal cross section were only approximately 6-7 characteristic lengths deep. After this reconstruction depth limit, features in the center of a domain begin to diminish independent of the number of experiments. When a small domain was considered and size held constant, the maximum reconstruction resolution for one group absorption or multi-group removal cross section is approximately one fourth of a characteristic length. When finer resolution then this is considered, there is simply not enough information to recover that many region's cross sections independent of number of experiments or flux to cross-section mesh refinement. When reconstructing fission cross sections, the one group case is identical to absorption so only the multi-group is considered, then the problem at hand becomes more ill-posed. A corresponding change in fission cross section from a change in boundary flux is much greater then change in removal cross section pushing convergence criteria to its limits. Due to a more ill-posed problem, the maximum reconstruction depth for multi-group fission cross sections is 5 characteristic lengths, which is significantly shorter than the removal limit. To better simulate actual detector readings, random signal noise and biased noise were added to the synthetic measured solutions produced by the forward models. The magnitude of this noise and biased noise is modified and a dependency of the maximum magnitude of this noise versus the size of a domain was established. As expected, the results showed that as a domain becomes larger its reconstruction ability is lowered which worsens upon the addition of noise and biased noise.en
dc.format.mimetypeapplication/pdf
dc.language.isoen_US
dc.subjectinverse neutron diffusionen
dc.subjectinverse problemsen
dc.subjectfinite elementen
dc.subjectinferen
dc.subjectreconstructen
dc.subjectNewton's methoden
dc.subjectmultigroup neutron diffusionen
dc.subjectoptimizationen
dc.titleApplication of a Constrained Optimization Technique to the Imaging of Heterogeneous Objects Using Diffusion Theoryen
dc.typeThesisen
thesis.degree.departmentNuclear Engineeringen
thesis.degree.disciplineNuclear Engineeringen
thesis.degree.grantorTexas A&M Universityen
thesis.degree.nameMaster of Scienceen
thesis.degree.levelMastersen
dc.contributor.committeeMemberBangerth, Wolfgang
dc.contributor.committeeMemberCharlton, William S.
dc.type.genrethesisen
dc.type.materialtexten


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