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dc.contributor.advisorBenoit Forget.en_US
dc.contributor.authorEverson, Matthew Sen_US
dc.contributor.otherMassachusetts Institute of Technology. Department of Nuclear Science and Engineering.en_US
dc.date.accessioned2014-05-23T17:13:47Z
dc.date.available2014-05-23T17:13:47Z
dc.date.copyright2014en_US
dc.date.issued2014en_US
dc.identifier.urihttp://hdl.handle.net/1721.1/87129
dc.descriptionThesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2014.en_US
dc.descriptionThis electronic version was submitted by the student author. The certified thesis is available in the Institute Archives and Special Collections.en_US
dc.descriptionCataloged from student-submitted PDF version of thesis.en_US
dc.descriptionIncludes bibliographical references (pages 249-252).en_US
dc.description.abstractFine-group whole-core reactor analysis remains one of the long sought goals of the reactor physics community. Such a detailed analysis is typically too computationally expensive to be realized on anything except the largest of supercomputers. Recondensation using the Discrete Generalized Multigroup (DGM) method, though, offers a relatively cheap alternative to solving the fine group transport problem. DGM, however, suffered from inconsistencies when applied to high-order spatial methods. Many different approaches were taken to rectify this problem. First, explicit spatial dependence was included in the group collapse process, thereby creating the first ever set of high-order spatial cross sections. While these cross sections were able to asymptotically improve the solution, exact consistency was not achieved. Second, the derivation of the DGM equations was instead applied to the transport equation once the spatial method had been applied, allowing for the definition of an exact corrective factor to drive recondensation to the exact fine-group solution. However, this approach requires excessive memory to be practical for realistic problems. Third, a new method called the Source Equivalence Acceleration Method (SEAM) was developed, which was able to form a coarse-group problem equivalent to the fine-group problem allowing recondensation to converge to the fine-group solution with minimal memory requirements and little additional overhead. SEAM was then implemented in OpenMOC, a 2D Method of Characteristics code developed at MIT, and its performance tested against Coarse Mesh Finite Difference (CMFD) acceleration. For extremely expensive transport calculations, SEAM was able to outperform CMFD, resulting in speed-ups of 20-45 relative to the normal power iteration calculation. Additionally, to address the growing interest in Krylov based solvers applied to reactor physics calculations, an energy-based preconditioner was developed that is inexpensive to form and can accelerate convergence.en_US
dc.description.statementofresponsibilityby Matthew S. Everson.en_US
dc.format.extent255 pagesen_US
dc.language.isoengen_US
dc.publisherMassachusetts Institute of Technologyen_US
dc.rightsM.I.T. theses are protected by copyright. They may be viewed from this source for any purpose, but reproduction or distribution in any format is prohibited without written permission. See provided URL for inquiries about permission.en_US
dc.rights.urihttp://dspace.mit.edu/handle/1721.1/7582en_US
dc.subjectNuclear Science and Engineering.en_US
dc.titleAdvanced application of the discrete generalized multigroup method and recondensation to reactor analysisen_US
dc.typeThesisen_US
dc.description.degreePh. D.en_US
dc.contributor.departmentMassachusetts Institute of Technology. Department of Nuclear Science and Engineering
dc.identifier.oclc879666669en_US


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