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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 Edward.en_US
dc.date.accessioned2005-09-13T19:02:52Z
dc.date.available2005-09-13T19:02:52Z
dc.date.copyright1977en_US
dc.date.issued1977en_US
dc.identifier.urihttp://hdl.handle.net/1721.1/16334en_US
dc.descriptionThesis: Sc. D., Massachusetts Institute of Technology, Department of Nuclear Engineering, 1977en_US
dc.descriptionIncludes bibliographical references.en_US
dc.format.extent161, [78] leavesen_US
dc.publisherMassachusetts Institute of Technologyen_US
dc.rightsMIT theses may be protected by copyright. Please reuse MIT thesis content according to the MIT Libraries Permissions Policy, which is available through the URL provided.en_US
dc.rights.urihttp://dspace.mit.edu/handle/1721.1/7582en_US
dc.subjectNuclear Engineeringen_US
dc.subject.lcshNuclear fuel elements Thermal properties.en_US
dc.subject.lcshNuclear fuel elements Computer programs.en_US
dc.titleImproved multidimensional numerical methods for the steady state and transient thermal-hydraulic analysis of fuel pin bundles and nuclear reactor cores.en_US
dc.typeThesisen_US
dc.description.degreeSc. D.en_US
dc.contributor.departmentMassachusetts Institute of Technology. Department of Nuclear Engineeringen_US
dc.identifier.oclc04029175en_US
dc.description.collectionSc. D. Massachusetts Institute of Technology, Department of Nuclear Engineeringen_US
dspace.imported2022-04-19T18:14:33Zen_US


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