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dc.contributor.advisorPeter Griffith.en_US
dc.contributor.authorCluss, Edward Maxen_US
dc.date.accessioned2005-06-02T13:20:08Z
dc.date.available2005-06-02T13:20:08Z
dc.date.issued1978en_US
dc.identifier.urihttp://hdl.handle.net/1721.1/17147
dc.descriptionThesis. 1978. M.S.--Massachusetts Institute of Technology. Dept. of Mechanical Engineering.en_US
dc.descriptionMICROFICHE COPY AVAILABLE IN ARCHIVES AND ENGINEERING.en_US
dc.descriptionIncludes bibliographical references.en_US
dc.description.statementofresponsibilityby Edward M. Cluss, Jr.en_US
dc.format.extent91 leavesen_US
dc.format.extent3274537 bytes
dc.format.extent3283042 bytes
dc.format.mimetypeapplication/pdf
dc.format.mimetypeapplication/pdf
dc.language.isoengen_US
dc.publisherMassachusetts Institute of Technologyen_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.subjectMechanical Engineeringen_US
dc.subject.lcshCriticality (Nuclear engineering)en_US
dc.subject.lcshHeat Transmissionen_US
dc.subject.lcshNuclear reactors Safety measuresen_US
dc.titlePost critical heat flux heat transfer in a vertical tube including spacer grid effectsen_US
dc.typeThesisen_US
dc.description.degreeM.S.en_US
dc.contributor.departmentMassachusetts Institute of Technology. Department of Mechanical Engineering
dc.identifier.oclc06753349en_US


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