Show simple item record

dc.contributor.advisorPavel Hejzlar.en_US
dc.contributor.authorCochran, Peter A. (Peter Andrew)en_US
dc.contributor.otherMassachusetts Institute of Technology. Dept. of Nuclear Engineering.en_US
dc.date.accessioned2006-11-07T12:21:30Z
dc.date.available2006-11-07T12:21:30Z
dc.date.copyright2005en_US
dc.date.issued2005en_US
dc.identifier.urihttp://hdl.handle.net/1721.1/34456
dc.descriptionThesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2005.en_US
dc.descriptionIncludes bibliographical references.en_US
dc.description.abstractThe goal of this thesis is to design an experimental thermal-hydraulic loop capable of generating accurate, reliable data in various convection heat transfer regimes for use in the formulation of a comprehensive convection heat transfer correlation. The initial focus of the design is to ensure that the loop will be able to generate the convection flow regimes found in post Loss of Coolant Accident (LOCA) operation of a Gas-cooled Fast Reactor (GFR). As a result a scaling analysis of the proposed test facility was undertaken to demonstrate that the proposed loop would be able to operate in these aforementioned regimes. Having verified that the experimental loop could operate in the regimes of interest the next stage in the project was construction of the loop. Following construction of the loop and necessary instrumentation, an uncertainty analysis of the facility was conducted with the goal of determining the uncertainty associated with the calculation of heat transfer coefficients from the experimental data. The initial results were discouraging as the uncertainty calculated was large, ranging from -10-60%. After performing a heat transfer coefficient uncertainty analysis, we observed that the bulk of the uncertainty was clue to heat loss from the fluid to the environment.en_US
dc.description.abstract(cont.) Therefore, guard heaters were implemented into the loop design, to match the inner surface temperature of the insulation to the wall temperature of the test section, which allows minimization of heat loss to about zero. This resulted in the considerable reduction in heat transfer coefficient uncertainty to -8-15%.en_US
dc.description.statementofresponsibilityby Peter A. Cochran.en_US
dc.format.extent85 leavesen_US
dc.format.extent3764234 bytes
dc.format.extent3767725 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.subjectNuclear Engineering.en_US
dc.titleDesign of an experimental loop for post-LOCA heat transfer regimes in a Gas-cooled Fast Reactoren_US
dc.title.alternativeExperimental loop for post-Loss of Coolant Accident heat transfer regimes in a GFRen_US
dc.typeThesisen_US
dc.description.degreeS.M.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.oclc70715422en_US


Files in this item

Thumbnail

This item appears in the following Collection(s)

Show simple item record