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dc.contributor.authorSims, Randall Neeen_US
dc.contributor.otherMassachusetts Institute of Technology. Department of Nuclear Engineeringen_US
dc.date.accessioned2014-09-16T23:36:40Z
dc.date.available2014-09-16T23:36:40Z
dc.date.issued1977en_US
dc.identifier.urihttp://hdl.handle.net/1721.1/89733
dc.description"August 1977."en_US
dc.descriptionSeries statement handwritten on spineen_US
dc.descriptionIncludes bibliographical referencesen_US
dc.format.extent578 pagesen_US
dc.publisherCambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1977]en_US
dc.relation.ispartofseriesMITNE ; no. 201en_US
dc.subject.lccTK9008.M41 N96 no.201en_US
dc.subject.lcshFinite element method -- Data processingen_US
dc.subject.lcshNeutron transport theoryen_US
dc.subject.lcshNuclear reactors -- Tablesen_US
dc.subject.lcshDifferential equationsen_US
dc.titleDescription of the two-dimensional nodal codes "NRMS," a multigroup static code, and "NRMT," a one- and two-group transient code for solution of the neutron diffusion equation in rectangular geometryen_US
dc.title.alternativeDescription of the 2D nodal codes "nodal response method static," a multigroup static code, and "nodal response method transient," a one- and two-group transient code for solution of the neutron diffusion equation in rectangular geometryen_US
dc.typeTechnical Reporten_US
dc.identifier.oclc857246759en_US


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