| dc.contributor.author |
Buongiorno, Jacopo, 1971- |
|
| dc.coverage.temporal |
Spring 2005 |
|
| dc.date.accessioned |
2009-03-05T06:04:50Z |
|
| dc.date.available |
2009-03-05T06:04:50Z |
|
| dc.date.issued |
2005-06 |
|
| dc.identifier |
22.313-Spring2005 |
|
| dc.identifier.other |
22.313 |
|
| dc.identifier.other |
IMSCP-MD5-20e2d1b2c534297d4f9ba754770f4be9 |
|
| dc.identifier.uri |
http://hdl.handle.net/1721.1/44637 |
|
| dc.description.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." |
en |
| dc.description.provenance |
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Previous issue date: 2005-06 |
en |
| dc.language.iso |
en-US |
|
| dc.relation.hasversion |
http://www.core.org.cn/OcwWeb/Nuclear-Engineering/22-313Thermal-Hydraulics-in-Nuclear-Power-TechnologySpring2003/CourseHome/index.htm |
|
| dc.relation.isbasedon |
http://hdl.handle.net/1721.1/35790 |
|
| dc.rights |
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. |
en |
| dc.subject |
reactor |
en |
| dc.subject |
nuclear reactor |
en |
| dc.subject |
thermal behavior |
en |
| dc.subject |
hydraulic |
en |
| dc.subject |
hydraulic behavior |
en |
| dc.subject |
heat |
en |
| dc.subject |
modeling |
en |
| dc.subject |
steam |
en |
| dc.subject |
stability |
en |
| dc.subject |
instability |
en |
| dc.subject |
thermo-fluid dynamic phenomena |
en |
| dc.subject |
single-heated channel-transient analysis |
en |
| dc.subject |
Multiple-heated channels |
en |
| dc.subject |
Loop analysis |
en |
| dc.subject |
single and two-phase natural circulation |
en |
| dc.subject |
Kinematics |
en |
| dc.subject |
two-phase flows |
en |
| dc.subject |
subchannel analysis |
en |
| dc.subject |
Core thermal analysis |
en |
| dc.title |
22.313 Thermal Hydraulics in Nuclear Power Technology, Spring 2005 |
en |
| dc.title.alternative |
Thermal Hydraulics in Nuclear Power Technology |
en |
| dc.audience.educationlevel |
Graduate |
|
| dc.subject.cip |
142301 |
en |
| dc.subject.cip |
Nuclear Engineering |
en |
