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The cylindrical cell approximation in thermal utilization

dc.contributor.authorZweifel, Paul Fredericken_US
dc.contributor.authorMannan, Muhammad A.en_US
dc.date.accessioned2006-04-17T16:13:14Z
dc.date.available2006-04-17T16:13:14Z
dc.date.issued1967-01en_US
dc.identifier.citationZweifel, P. F., Mannan, M. A. (1967/01)."The cylindrical cell approximation in thermal utilization." Journal of Nuclear Energy 21(1): 1-6. <http://hdl.handle.net/2027.42/33375>en_US
dc.identifier.urihttp://www.sciencedirect.com/science/article/B75CY-49N3D7N-28/2/98560cb5106bbf3c592a0bc1e663b5f1en_US
dc.identifier.urihttps://hdl.handle.net/2027.42/33375
dc.description.abstractIn solving the neutron diffusion equation in one cell of an infinite lattice, a common procedure is to replace the rectangular (or hexagonal) cell with an equivalent cylindrical cell. In order to estimate the effect of this approximation a new method is presented in which the flux in the entire cell (not the equivalent cylindrical cell) is expanded in a Fourier cosine series. Then the boundary conditions over the cell surface are satisfied exactly. Furthermore, algebraic equations for the expansion coefficients of the flux are obtained because the integrals over the cell can be done in closed form. It is found that truncation of the flux series after 10 terms gives good results. The method is felt to have more general application than to the actual problem treated here since such `mixed geometry' problems frequently arise in reactor physics and in other areas as well.en_US
dc.format.extent424334 bytes
dc.format.extent3118 bytes
dc.format.mimetypeapplication/pdf
dc.format.mimetypetext/plain
dc.language.isoen_US
dc.publisherElsevieren_US
dc.titleThe cylindrical cell approximation in thermal utilizationen_US
dc.typeArticleen_US
dc.rights.robotsIndexNoFollowen_US
dc.subject.hlbsecondlevelPhysicsen_US
dc.subject.hlbsecondlevelNuclear Engineering and Radiological Sciencesen_US
dc.subject.hlbtoplevelScienceen_US
dc.subject.hlbtoplevelEngineeringen_US
dc.description.peerreviewedPeer Revieweden_US
dc.contributor.affiliationumThe University of Michigan, Ann Arbor, Michigan, USAen_US
dc.contributor.affiliationumThe University of Michigan, Ann Arbor, Michigan, USAen_US
dc.description.bitstreamurlhttp://deepblue.lib.umich.edu/bitstream/2027.42/33375/1/0000773.pdfen_US
dc.identifier.doihttp://dx.doi.org/10.1016/0022-3107(67)90030-5en_US
dc.identifier.sourceJournal of Nuclear Energyen_US
dc.owningcollnameInterdisciplinary and Peer-Reviewed


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