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22.313 Thermal Hydraulics in Nuclear Power Technology, Spring 2003

dc.contributor.authorTodreas, Neil E.en_US
dc.coverage.temporalSpring 2003en_US
dc.date.issued2003-06
dc.identifier22.313-Spring2003
dc.identifierlocal: 22.313
dc.identifierlocal: IMSCP-MD5-27bf08aa2071a09705856070cfab3e60
dc.identifier.urihttp://hdl.handle.net/1721.1/35790
dc.description.abstractAdvanced topics emphasizing thermo-fluid dynamic phenomena and analysis methods. Single-heated channel-transient analysis. Multiple-heated channels connected at plena. Loop analysis including single and two-phase natural circulation. Kinematics and dynamics of two-phase flows with energy addition. Boiling, instabilities, and critical conditions. Subchannel analysis.en_US
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dc.languageen-USen_US
dc.rights.uriUsage Restrictions: This site (c) Massachusetts Institute of Technology 2003. Content within individual courses is (c) by the individual authors unless otherwise noted. The Massachusetts Institute of Technology is providing this Work (as defined below) under the terms of this Creative Commons public license ("CCPL" or "license"). The Work is protected by copyright and/or other applicable law. Any use of the work other than as authorized under this license is prohibited. By exercising any of the rights to the Work provided here, You (as defined below) accept and agree to be bound by the terms of this license. The Licensor, the Massachusetts Institute of Technology, grants You the rights contained here in consideration of Your acceptance of such terms and conditions.en_US
dc.subjectthermo-fluid dynamic phenomenaen_US
dc.subjectSingle-heated channel-transient analysisen_US
dc.subjectMultiple-heated channelsen_US
dc.subjectLoop analysisen_US
dc.subjectsingle and two-phase natural circulationen_US
dc.subjectKinematicsen_US
dc.subjecttwo-phase flowsen_US
dc.subjectSubchannel analysis. Core thermal analysisen_US
dc.subjectHydraulicsen_US
dc.subjectNuclear energyen_US
dc.title22.313 Thermal Hydraulics in Nuclear Power Technology, Spring 2003en_US
dc.title.alternativeThermal Hydraulics in Nuclear Power Technologyen_US


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