Login

22.313 Thermal Hydraulics in Nuclear Power Technology, Spring 2003

Show full item record




Title: 22.313 Thermal Hydraulics in Nuclear Power Technology, Spring 2003
Author: Todreas, Neil E.
Issue Date: 2003-06
Abstract: 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. Boiling, instabilities, and critical conditions. Subchannel analysis.
URI: http://hdl.handle.net/1721.1/35790
Other Identifiers: 22.313-Spring2003
Other Identifiers: 22.313
IMSCP-MD5-27bf08aa2071a09705856070cfab3e60
Keywords: 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, 142301, Nuclear Engineering

Files in this item

Files Size Format View
22-313Spring-20 ... g2003/CourseHome/index.htm 15.12Kb HTML View/Open

The following license files are associated with this item:

This item appears in the following Collection(s)

Show full item record

Search DSpace@MIT


Advanced Search

Browse

My Account

Links