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dc.contributor.authorGoellner, D.en_US
dc.contributor.authorBeaudreau, James Josephen_US
dc.contributor.otherMassachusetts Institute of Technology. Department of Nuclear Engineeringen_US
dc.date.accessioned2014-09-15T18:14:58Z
dc.date.available2014-09-15T18:14:58Z
dc.date.issued1968en_US
dc.identifier.urihttp://hdl.handle.net/1721.1/89593
dc.description"MIT-2073-8."en_US
dc.descriptionIncludes bibliographical references (pages 85-66)en_US
dc.description.sponsorshipContract AT(30-1)-2073en_US
dc.format.extent66 pagesen_US
dc.publisherCambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1968en_US
dc.relation.ispartofseriesMIT-2073-8en_US
dc.relation.ispartofseriesMITNE ; no. 89en_US
dc.subject.lccTK9008.M41 N96 no.89en_US
dc.subject.lcshNuclear reactors -- Computer programsen_US
dc.subject.lcshNuclear fuelsen_US
dc.titleSummary description of the fuel depletion code, CELLen_US
dc.typeTechnical Reporten_US
dc.identifier.oclc13994693en_US


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