22.313 Thermal Hydraulics in Nuclear Power Technology, Spring 2005
Name
22-313Spring-2005/OcwWeb/Nuclear-Engineering/22-313Spring-2005/CourseHome/index.htm
Size
15.13 KB
Format
HTML
Checksum (MD5)
715362c5869506792051a998f9a07265
Author(s)
Buongiorno, Jacopo, 1971-
Alternative Title
Thermal Hydraulics in Nuclear Power Technology
Date Issued
June 2005
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. From the course home page: Course Description This course covers the thermo-fluid dynamic phenomena and analysis methods for conventional and nuclear power stations. Specific topics include: kinematics and dynamics of two-phase flows; steam separation; boiling, instabilities, and critical conditions; single-channel transient analysis; multiple channels connected at plena; loop analysis including single and two-phase natural circulation; and subchannel analysis. Starting in Spring 2007, this course will be offered jointly in the Departments of Nuclear Science and Engineering, Mechanical Engineering, and Chemical Engineering, and will be titled "Thermal Hydraulics in Power Technology."
Subjects
reactor
nuclear reactor
thermal behavior
hydraulic
hydraulic behavior
heat
modeling
steam
stability
instability
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
MIT Department
Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
Terms of Use
Persistent DSpace Link
