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dc.contributor.authorRoberts, Jeremy Alyn
dc.contributor.authorForget, Benoit Robert Yves
dc.date.accessioned2017-04-19T17:05:30Z
dc.date.available2017-04-19T17:05:30Z
dc.date.issued2014-02
dc.date.submitted2014-02
dc.identifier.issn03064549
dc.identifier.urihttp://hdl.handle.net/1721.1/108255
dc.description.abstractThis paper presents new algorithms for use in the eigenvalue response matrix method (ERMM) for reactor eigenvalue problems. ERMM spatially decomposes a domain into independent nodes linked via boundary conditions approximated as truncated orthogonal expansions, the coefficients of which are response functions. In its simplest form, ERMM consists of a two-level eigenproblem: an outer Picard iteration updates the k -eigenvalue via balance, while the inner λλ-eigenproblem imposes neutron balance between nodes. Efficient methods are developed for solving the inner λλ-eigenvalue problem within the outer Picard iteration. Based on results from several diffusion and transport benchmark models, it was found that the Krylov–Schur method applied to the λλ-eigenvalue problem reduces Picard solver times (excluding response generation) by a factor of 2–5. Furthermore, alternative methods, including Picard acceleration schemes, Steffensen’s method, and Newton’s method, are developed in this paper. These approaches often yield faster k-convergence and a need for fewer k-dependent response function evaluations, which is important because response generation is often the primary cost for problems using responses computed online (i.e., not from a precomputed database). Accelerated Picard iteration was found to reduce total computational times by 2–3 compared to the unaccelerated case for problems dominated by response generation. In addition, Newton’s method was found to provide nearly the same performance with improved robustness.en_US
dc.description.sponsorshipUnited States. Department of Energy (Nuclear Energy University Programs Graduate Fellowshi)en_US
dc.language.isoen_US
dc.publisherElsevieren_US
dc.relation.isversionofhttp://dx.doi.org/10.1016/j.anucene.2014.02.002en_US
dc.rightsCreative Commons Attribution-NonCommercial-NoDerivs Licenseen_US
dc.rights.urihttp://creativecommons.org/licenses/by-nc-nd/4.0/en_US
dc.sourceProf. Forget via Chris Sherratten_US
dc.titleSolving eigenvalue response matrix equations with nonlinear techniquesen_US
dc.typeArticleen_US
dc.identifier.citationRoberts, Jeremy A., and Benoit Forget. “Solving Eigenvalue Response Matrix Equations with Nonlinear Techniques.” Annals of Nuclear Energy 69 (July 2014): 97–107.en_US
dc.contributor.departmentMassachusetts Institute of Technology. Department of Nuclear Science and Engineeringen_US
dc.contributor.approverforget benoiten_US
dc.contributor.mitauthorRoberts, Jeremy Alyn
dc.contributor.mitauthorForget, Benoit Robert Yves
dc.relation.journalAnnals of Nuclear Energyen_US
dc.eprint.versionAuthor's final manuscripten_US
dc.type.urihttp://purl.org/eprint/type/JournalArticleen_US
eprint.statushttp://purl.org/eprint/status/PeerRevieweden_US
dspace.orderedauthorsRoberts, Jeremy A.; Forget, Benoiten_US
dspace.embargo.termsNen_US
dc.identifier.orcidhttps://orcid.org/0000-0003-1459-7672
mit.licensePUBLISHER_CCen_US


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