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Improved multidimensional numerical methods for the steady state and transient thermal-hydraulic analysis of fuel pin bundles and nuclear reactor cores

dc.contributor.authorMasterson, Robert Edwarden_US
dc.contributor.authorWolf Lotharen_US
dc.contributor.otherMassachusetts Institute of Technology. Department of Nuclear Engineeringen_US
dc.date.accessioned2014-09-12T23:53:21Z
dc.date.available2014-09-12T23:53:21Z
dc.date.issued1977en_US
dc.identifier.urihttp://hdl.handle.net/1721.1/89506
dc.descriptionOriginally presented as the first author's thesis, (Sc. D.)--in the M.I.T. Dept. of Nuclear Engineering, 1977en_US
dc.descriptionIncludes bibliographical referencesen_US
dc.format.extent164 p.en_US
dc.publisherCambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1977en_US
dc.relation.ispartofseriesMITNE ; no. 203en_US
dc.subject.lccTK9008.M41 N96 no.203en_US
dc.subject.lcshNuclear fuel elements -- Thermal propertiesen_US
dc.subject.lcshNuclear fuel elements -- Computer programsen_US
dc.titleImproved multidimensional numerical methods for the steady state and transient thermal-hydraulic analysis of fuel pin bundles and nuclear reactor coresen_US
dc.typeTechnical Reporten_US
dc.identifier.oclc04401770en_US


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