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Multiscale Methods for Nuclear Reactor Analysis.

dc.contributor.authorCollins, Benjamin S.en_US
dc.date.accessioned2012-01-26T20:06:58Z
dc.date.availableNO_RESTRICTIONen_US
dc.date.available2012-01-26T20:06:58Z
dc.date.issued2011en_US
dc.date.submitteden_US
dc.identifier.urihttps://hdl.handle.net/2027.42/89812
dc.description.abstractThe ability to accurately predict local pin powers in nuclear reactors is necessary to understand the mechanisms that cause fuel pin failure during steady state and transient operation. In the research presented here, methods are developed to improve the local solution using high order methods with boundary conditions from a low order global solution. Several different core configurations were tested to determine the improvement in the local pin powers compared to the standard techniques, that use diffusion theory and pin power reconstruction (PPR). Two different multiscale methods were developed and analyzed; the post-refinement multiscale method and the embedded multiscale method. The post-refinement multiscale methods use the global solution to determine boundary conditions for the local solution. The local solution is solved using either a fixed boundary source or an albedo boundary condition; this solution has no impact on the global solution. The embedded multiscale method allows the local solver to change the global solution to provide an improved global and local solution. The post-refinement multiscale method is assessed using three core designs. When the local solution has more energy groups, the fixed source method has some difficulties near the interface; however the albedo method works well for all cases. In order to remedy the issue with boundary condition errors for the fixed source method, a buffer region is used to act as a filter, which decreases the sensitivity of the solution to the boundary condition. Unlike the post-refinement method, the embedded multiscale method alters the global solution. The ability to change the global solution allows for refinement in areas where the errors in the few group nodal diffusion are typically large. The embedded method is shown to improve the global solution when it is applied to a MOX/LEU assembly interface, the fuel/reflector interface, and assemblies where control rods are inserted. The embedded method also allows for multiple solution levels to be applied in a single calculation. The addition of intermediate levels to the solution improves the accuracy of the method. Both multiscale methods considered here have benefits and drawbacks, but both can provide improvements over the current PPR methodology.en_US
dc.language.isoen_USen_US
dc.subjectNeutron Transport Methodsen_US
dc.subjectMultiscale Modelingen_US
dc.titleMultiscale Methods for Nuclear Reactor Analysis.en_US
dc.typeThesisen_US
dc.description.thesisdegreenamePhDen_US
dc.description.thesisdegreedisciplineNuclear Engineering and Radiological Sciences and Scientifen_US
dc.description.thesisdegreegrantorUniversity of Michigan, Horace H. Rackham School of Graduate Studiesen_US
dc.contributor.committeememberDownar, Thomas J.en_US
dc.contributor.committeememberSeker, Volkanen_US
dc.contributor.committeememberJohnsen, Ericen_US
dc.contributor.committeememberJoo, Han Gyuen_US
dc.contributor.committeememberLarsen, Edwarden_US
dc.contributor.committeememberMartin, William R.en_US
dc.contributor.committeememberXu, Yunlinen_US
dc.subject.hlbsecondlevelNuclear Engineering and Radiological Sciencesen_US
dc.subject.hlbtoplevelEngineeringen_US
dc.description.bitstreamurlhttp://deepblue.lib.umich.edu/bitstream/2027.42/89812/1/bscollin_1.pdf
dc.owningcollnameDissertations and Theses (Ph.D. and Master's)


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