22.313 Thermal Hydraulics in Nuclear Power Technology, Spring 2003

22.313 Thermal Hydraulics in Nuclear Power Technology, Spring 2003

Advanced 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. B...

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Bibliographic Details
Main Author: Todreas, Neil E.
Other Authors: Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
Format: Learning Object
Language:en-US
Published: 2003
Subjects:
thermo-fluid dynamic phenomena
Single-heated channel-transient analysis
Multiple-heated channels
Loop analysis
single and two-phase natural circulation
Kinematics
two-phase flows
Subchannel analysis. Core thermal analysis
Hydraulics
Nuclear energy
Online Access:http://hdl.handle.net/1721.1/35790

Internet

http://hdl.handle.net/1721.1/35790

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