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dc.contributor.authorShin, Jae Inen_US
dc.contributor.authorDriscoll Michael J.en_US
dc.contributor.otherMassachusetts Institute of Technology. Department of Nuclear Engineeringen_US
dc.contributor.otherU.S. Atomic Energy Commissionen_US
dc.date.accessioned2014-09-12T23:53:04Z
dc.date.available2014-09-12T23:53:04Z
dc.date.issued1977en_US
dc.identifier.urihttp://hdl.handle.net/1721.1/89503
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 references (p. 321-325)en_US
dc.description.sponsorshipERDA research and development E(11-1)-2250 UC-79P LMFBR-Physicsen_US
dc.format.extent325 p.en_US
dc.publisherCambridge, [Mass.] : Massachusetts Institute of Technology, 1977en_US
dc.relation.ispartofseriesMITNE ; no. 199en_US
dc.relation.ispartofseriesCOO ; 2250-25en_US
dc.subject.lccTK9008.M41 N96 no.199en_US
dc.subject.lcshFast reactorsen_US
dc.subject.lcshBreeder reactorsen_US
dc.subject.lcshNuclear fuel elementsen_US
dc.titleEvaluation of advanced fast reactor blanket designsen_US
dc.typeTechnical Reporten_US
dc.identifier.oclc04240518en_US


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