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dc.contributor.advisorPeter Griffith.en_US
dc.contributor.authorWalkush, Joseph Patricken_US
dc.date.accessioned2008-01-10T15:45:36Z
dc.date.available2008-01-10T15:45:36Z
dc.date.issued1975en_US
dc.identifier.urihttp://hdl.handle.net/1721.1/39854
dc.descriptionThesis. 1975. M.S.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering.en_US
dc.descriptionIncludes bibliographical references.en_US
dc.description.abstractThis is a report of the experimental results of a program in countercurrent flow critical heat flux. These experiments were performed with Freon 113 at 200 psia in order to model a high pressure water system. An internally heated annulus was used to model a fuel pin in a channel. Only low flowrates were examined. The flow regime was always bubbly or slug, with the liquid primarily on the walls. It was found that critical heat flux of about .9 of the pool boiling value can be expected for up to 20% void. Beyond this, the CHF value decreases uniformly with void. Void fractions up to 70% were investigated, with the results being slightly conservative compared to a similar experiment carried out at atmospheric pressure by Avedisian.en_US
dc.format.extent56 leavesen_US
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.subjectNuclear Engineeringen_US
dc.subject.lcshPressurized water reactorsen_US
dc.subject.lcshNuclear reactor accidentsen_US
dc.titleHigh pressure counterflow CHF.en_US
dc.typeThesisen_US
dc.description.degreeM.S.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.oclc01282141en_US


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