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dc.contributor.advisorAllan F. Henry.en_US
dc.contributor.authorSmith, Kord Sterlingen_US
dc.date.accessioned2005-08-04T15:32:53Z
dc.date.available2005-08-04T15:32:53Z
dc.date.copyright1979en_US
dc.date.issued1979en_US
dc.identifier.urihttp://hdl.handle.net/1721.1/15979
dc.descriptionThesis (Nucl.E.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1979.en_US
dc.descriptionMICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE.en_US
dc.descriptionIncludes bibliographical references.en_US
dc.description.statementofresponsibilityby Kord S. Smith.en_US
dc.format.extent283 leaves in various foliationsen_US
dc.format.extent15409029 bytes
dc.format.extent15408785 bytes
dc.format.mimetypeapplication/pdf
dc.format.mimetypeapplication/pdf
dc.language.isoengen_US
dc.publisherMassachusetts Institute of Technologyen_US
dc.relation.ispartofseriesMassachusetts Institute of Technology. Dept. of Nuclear Engineering.en_US
dc.rightsM.I.T. theses are protected by copyright. They may be viewed from this source for any purpose, but reproduction or distribution in any format is prohibited without written permission. See provided URL for inquiries about permission.en_US
dc.rights.urihttp://dspace.mit.edu/handle/1721.1/7582
dc.subjectNuclear Engineeringen_US
dc.subject.lcshNeutron transport theoryen_US
dc.subject.lcshNuclear reactors Tablesen_US
dc.titleAn analytic nodal method for solving the two-group, multidimensional, static and transient neutron diffusion equationsen_US
dc.typeThesisen_US
dc.description.degreeNucl.E.en_US
dc.contributor.departmentMassachusetts Institute of Technology. Department of Nuclear Engineeringen_US
dc.contributor.departmentMassachusetts Institute of Technology. Department of Nuclear Science and Engineering
dc.identifier.oclc07057754en_US


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