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Adjoint sensitivity analysis in nuclear reactor fuel behavior modeling

dc.contributor.authorChristensen, Ronald A.en_US
dc.contributor.authorEilbert, Richard F.en_US
dc.contributor.authorRohrer, Ronald A.en_US
dc.contributor.authorWas, Gary S.en_US
dc.date.accessioned2006-04-07T18:03:07Z
dc.date.available2006-04-07T18:03:07Z
dc.date.issued1981-08en_US
dc.identifier.citationChristensen, Ronald A., Eilbert, Richard F., Rohrer, Ronald A., Was, Gary S. (1981/08)."Adjoint sensitivity analysis in nuclear reactor fuel behavior modeling." Nuclear Engineering and Design 66(1): 125-139. <http://hdl.handle.net/2027.42/24288>en_US
dc.identifier.urihttp://www.sciencedirect.com/science/article/B6V4D-47RSG5H-C/2/1bbe1d8936e718f8c400868a11db8a22en_US
dc.identifier.urihttps://hdl.handle.net/2027.42/24288
dc.description.abstractA computer program, SCODE, has been developed for calculating sensitivities for EPRI's SPEAR-ALPHA nuclear fuel performance code FCODE-ALPHA. Eleven critical parameters are assessed for the effects of their independent variations on 33 basic variables in the FCODE-ALPHA model. The enormous wealth of sensitivities that result, consisting of 363 quantities per axial node per time step, are calculated following FCODE-ALPHA computations on each time step. SCODE is based on adjoint sensitivity analysis, which is an analytic technique, obviating the need for numerical differentiation via repeated code runs at varied parameter values. Evaluation of sensitivities is reduced to a problem in linear algebra and is handled by standard matrix manipulations. Compared with the customary numerical differentiation approach, SCODE offers advantages of significant runtime reduction, exactitude of results, and on-line computation of sensitivities.en_US
dc.format.extent868658 bytes
dc.format.extent3118 bytes
dc.format.mimetypeapplication/pdf
dc.format.mimetypetext/plain
dc.language.isoen_US
dc.publisherElsevieren_US
dc.titleAdjoint sensitivity analysis in nuclear reactor fuel behavior modelingen_US
dc.typeArticleen_US
dc.rights.robotsIndexNoFollowen_US
dc.subject.hlbsecondlevelNuclear Engineering and Radiological Sciencesen_US
dc.subject.hlbtoplevelEngineeringen_US
dc.description.peerreviewedPeer Revieweden_US
dc.contributor.affiliationumUniversity of Michigan, Department of Nuclear Engineering, Ann Arbor, MI 48109, USAen_US
dc.contributor.affiliationotherEntropy Limited, South Great Road, Lincoln, MA 01773, USAen_US
dc.contributor.affiliationotherEntropy Limited, South Great Road, Lincoln, MA 01773, USAen_US
dc.contributor.affiliationotherUniversity of Colorado, Department of Electrical Engineering, Computer Science, Colorado Springs, CO 80906, USAen_US
dc.description.bitstreamurlhttp://deepblue.lib.umich.edu/bitstream/2027.42/24288/1/0000554.pdfen_US
dc.identifier.doihttp://dx.doi.org/10.1016/0029-5493(81)90186-2en_US
dc.identifier.sourceNuclear Engineering and Designen_US
dc.owningcollnameInterdisciplinary and Peer-Reviewed


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