22.313 Thermal Hydraulics in Nuclear Power Technology, Spring 2003

Todreas, Neil E.

Author(s)

Todreas, Neil E.

Download22-313Spring-2003/OcwWeb/Nuclear-Engineering/22-313Thermal-Hydraulics-in-Nuclear-Power-TechnologySpring2003/CourseHome/index.htm (14.78Kb)

Alternative title

Thermal Hydraulics in Nuclear Power Technology

Terms of use

Usage 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.

Metadata

Show full item record

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

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

Collections

Nuclear Science and Engineering (22) - Archived