Advanced Search
DSpace@MIT

Friction pressure drop measurements and flow distribution analysis for LEU conversion study of MIT Research Reactor

Research and Teaching Output of the MIT Community

Show simple item record

dc.contributor.advisor Lin-wen Hu and Mujid S. Kazimi. en_US
dc.contributor.author Wong, Susanna Yuen-Ting en_US
dc.contributor.other Massachusetts Institute of Technology. Dept. of Nuclear Science and Engineering. en_US
dc.date.accessioned 2010-03-25T15:24:30Z
dc.date.available 2010-03-25T15:24:30Z
dc.date.copyright 2008 en_US
dc.date.issued 2008 en_US
dc.identifier.uri http://hdl.handle.net/1721.1/53275
dc.description Thesis (S.M. and S.B.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2008. en_US
dc.description Page no. "2" used twice. Cataloged from PDF version of thesis. en_US
dc.description Includes bibliographical references (p. 147-150 [i.e. p. 148-151]). en_US
dc.description.abstract The MIT Nuclear Research Reactor (MITR) is the only research reactor in the United States that utilizes plate-type fuel elements with longitudinal fins to augment heat transfer. Recent studies on the conversion to low-enriched uranium (LEU) fuel at the MITR, together with the supporting thermal hydraulic analyses, propose different fuel element designs for optimization of thermal hydraulic performance of the LEU core. Since proposed fuel design has a smaller coolant channel height than the existing HEU fuel, the friction pressure drop is required to be verified experimentally. The objectives of this study are to measure the friction coefficient in both laminar and turbulent flow regions, and to develop empirical correlations for the finned rectangular coolant channels for the safety analysis of the MITR. A friction pressure drop experiment is set-up at the MIT Nuclear Reactor Laboratory, where static differential pressure is measured for both flat and finned coolant channels of various channel heights. Experiment data show that the Darcy friction factors for laminar flow in finned rectangular channels are in good agreement with the existing correlation if a pseudo-smooth equivalent hydraulic diameter is considered; whereas a new friction factor correlation is proposed for the friction factors for turbulent flow. Additionally, a model is developed to calculate the primary flow distribution in the reactor core for transitional core configuration with various combinations of HEU and LEU fuel elements. en_US
dc.description.statementofresponsibility by Susanna Yuen-Ting Wong. en_US
dc.format.extent 150 [i.e. 151] p. en_US
dc.language.iso eng en_US
dc.publisher Massachusetts Institute of Technology en_US
dc.rights M.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.uri http://dspace.mit.edu/handle/1721.1/7582 en_US
dc.subject Nuclear Science and Engineering. en_US
dc.title Friction pressure drop measurements and flow distribution analysis for LEU conversion study of MIT Research Reactor en_US
dc.type Thesis en_US
dc.description.degree S.M.and S.B. en_US
dc.contributor.department Massachusetts Institute of Technology. Dept. of Nuclear Science and Engineering. en_US
dc.identifier.oclc 547275119 en_US


Files in this item

Name Size Format Description
547275119.pdf 22.09Mb PDF Preview, non-printable (open to all)
547275119-MIT.pdf 22.09Mb PDF Full printable version (MIT only)

This item appears in the following Collection(s)

Show simple item record

MIT-Mirage