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dc.contributor.authorDeppe, Lothario Olavoen_US
dc.contributor.authorHansen Kent F.en_US
dc.contributor.otherMassachusetts Institute of Technology. Department of Nuclear Engineeringen_US
dc.contributor.otherUnited States. Department of Energyen_US
dc.date.accessioned2014-09-12T23:51:33Z
dc.date.available2014-09-12T23:51:33Z
dc.date.issued1973en_US
dc.identifier.urihttp://hdl.handle.net/1721.1/89493
dc.descriptionOriginally presented as the first author's thesis (Nucl. Eng.)--Massachusetts Institute of Technology Dept. of Nuclear Engineering, 1973en_US
dc.descriptionIncludes bibliographical references (pages 99-100)en_US
dc.format.extent123 pagesen_US
dc.publisherCambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1973en_US
dc.relation.ispartofseriesMITNE ; no. 145en_US
dc.relation.ispartofseriesCOO ; 2262-1en_US
dc.subject.lccTK9008.M41 N96 no.145en_US
dc.subject.lcshFinite element methoden_US
dc.subject.lcshNuclear reactor kineticsen_US
dc.subject.lcshNeutron transport theoryen_US
dc.subject.lcshNuclear reactors -- Computer programsen_US
dc.titleThe finite element method applied to neutron diffusion problemsen_US
dc.typeTechnical Reporten_US
dc.identifier.oclc02294061en_US


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