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dc.contributor.advisorKord S. Smith and Benoit Forget.en_US
dc.contributor.authorHerman, Bryan R. (Bryan Robert)en_US
dc.contributor.otherMassachusetts Institute of Technology. Department of Nuclear Science and Engineering.en_US
dc.date.accessioned2015-02-25T16:43:40Z
dc.date.available2015-02-25T16:43:40Z
dc.date.copyright2014en_US
dc.date.issued2014en_US
dc.identifier.urihttp://hdl.handle.net/1721.1/95525
dc.descriptionThesis: Sc. 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 143-147).en_US
dc.description.abstractMonte Carlo (MC) methods for reactor analysis are most often employed as a benchmark tool for other transport and diffusion methods. In this work, we identify and resolve a few of the issues associated with using MC as a reactor design tool. It is widely thought that MC tallies converge at an ideal rate proportional to the inverse of the square root of the number of tally batches. This is true only if tally batches are independent from one another. For a high dominance ratio light water reactor such as the BEAVRS model, significant correlation is present and the convergence rate was much slower. This work developed a means for analytically predicting tally convergence rates when batches are correlated. Analyses supported these findings and confirmed less than ideal convergence rates. For highly correlated problems, it is recommended to reduce error by running additional independent simulations, rather than increasing the number of neutrons in each individual simulation through additional batches. Before tallies can be accumulated, the fission source must be stationary. For the BEAVRS model, this took approximately 200 fission source generations. This process can be accelerated by using coarse mesh finite difference (CMFD), a nonlinear diffusion acceleration method. CMFD was implemented in the continuous-energy MC code OpenMC. When employing this technique, the number of inactive generations was reduced by a factor of 10. Realistic reactor calculations also require thermal hydraulic (TH) feedback which was integrated into the source convergence process. The use of CMFD in addition to TH reduced the number of fission source generations by a factor of 3. Further reduction was achieved by performing nonlinear iterations between the low-order CMFD operator and TH model. Support vector regression, a machine learning algorithm, was used to construct coolant density and fuel temperature dependencies of diffusion parameters between each TH update using MC tallies. A framework was introduced to obtain relative pin power distributions with 95% confidence intervals to 1% with continuous-energy Monte Carlo coupled to thermal hydraulics using low-order CMFD iterations.en_US
dc.description.statementofresponsibilityby Bryan Robert Herman.en_US
dc.format.extent147 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.titleMonte Carlo and thermal hydraulic coupling using low-order nonlinear diffusion accelerationen_US
dc.title.alternativeMC and thermal hydraulic coupling using low-order nonlinear diffusion accelerationen_US
dc.typeThesisen_US
dc.description.degreeSc. D.en_US
dc.contributor.departmentMassachusetts Institute of Technology. Department of Nuclear Science and Engineering
dc.identifier.oclc903706100en_US


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