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dc.contributor.authorRodack, Thomasen_US
dc.contributor.authorWolf, Lotharen_US
dc.contributor.otherMassachusetts Institute of Technology. Department of Nuclear Engineeringen_US
dc.date.accessioned2014-09-16T23:36:51Z
dc.date.available2014-09-16T23:36:51Z
dc.date.issued1977en_US
dc.identifier.urihttp://hdl.handle.net/1721.1/89734
dc.descriptionCover titleen_US
dc.description"August 1977."en_US
dc.descriptionAlso issued as a Nucl. E. and M.S. thesis by the first author and supervised by the second author, MIT Depts. of Nuclear and Mechanical Engineering, 1977en_US
dc.descriptionIncludes bibliographical references (pages 242-246)en_US
dc.description.abstractThe thermal-hydraulic (T-H) models and solution schemes employed by the MEKIN computer code have been examined. The effects of T-H input parameters on- predicted fuel temperatures and coolant densities were determined in transient analyses. Consideration was limited primarily to a simulated PWR control rod ejection transient. Limitations to the use of MEKIN that arise because of simplifying assumptions in the T-H models are discussed. Computation time may be reduced without altering the results of a transient analysis if appropriate MEKIN options are selected. Guidelines are presented to facilitate the selection of these options. Suggestions for improvement of the code are also ma:de.en_US
dc.format.extent283 pagesen_US
dc.publisherCambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, [1977]en_US
dc.relation.ispartofseriesMITNE ; no. 206en_US
dc.subject.lccTK9008.M41 N96 no.206en_US
dc.subject.lcshNuclear fuel elements -- Computer programsen_US
dc.subject.lcshNuclear fuel elements -- Thermal propertiesen_US
dc.subject.lcshNuclear reactors -- Fluid dynamicsen_US
dc.titleSensitivity study of the assembly averaged thermal-hydraulic models of the MEKIN computer code in power transients / by Thomas Rodack [and] Lothar Wolfen_US
dc.typeTechnical Reporten_US
dc.identifier.oclc857286221en_US


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