22.313 Thermal Hydraulics in Nuclear Power Technology, Spring 2003

Todreas, Neil E.

Author(s)

Todreas, Neil E.

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Alternative title

Thermal Hydraulics in Nuclear Power Technology

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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.

Date issued

2003-06

URI

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

Department

Massachusetts Institute of Technology. Department of Nuclear Science and Engineering

Other identifiers

22.313-Spring2003

local: 22.313

local: 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

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