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22.313 Thermal Hydraulics in Nuclear Power Technology (MIT) 22.313 Thermal Hydraulics in Nuclear Power Technology (MIT)

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." 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 | reactor | nuclear reactor | nuclear reactor | thermal behavior | thermal behavior | hydraulic | hydraulic | hydraulic behavior | hydraulic behavior | heat | heat | modeling | modeling | steam | steam | stability | stability | instability | instability | thermo-fluid dynamic phenomena | thermo-fluid dynamic phenomena | single-heated channel-transient analysis | single-heated channel-transient analysis | Multiple-heated channels | Multiple-heated channels | Loop analysis | Loop analysis | single and two-phase natural circulation | single and two-phase natural circulation | Kinematics | Kinematics | two-phase flows | two-phase flows | subchannel analysis | subchannel analysis | Core thermal analysis | Core thermal analysis

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see http://ocw.mit.edu/terms/index.htm

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22.313 Thermal Hydraulics in Nuclear Power Technology (MIT) 22.313 Thermal Hydraulics in Nuclear Power Technology (MIT)

Description

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. Core thermal analysis approaches. 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. Core thermal analysis approaches.

Subjects

thermo-fluid dynamic phenomena | thermo-fluid dynamic phenomena | Single-heated channel-transient analysis | Single-heated channel-transient analysis | Multiple-heated channels | Multiple-heated channels | Loop analysis | Loop analysis | single and two-phase natural circulation | single and two-phase natural circulation | Kinematics | Kinematics | two-phase flows | two-phase flows | Subchannel analysis | Subchannel analysis | Core thermal analysis | Core thermal analysis | Subchannel analysis. Core thermal analysis | Subchannel analysis. Core thermal analysis

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see http://ocw.mit.edu/terms/index.htm

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22.313J Thermal Hydraulics in Power Technology (MIT) 22.313J Thermal Hydraulics in Power Technology (MIT)

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. 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.

Subjects

reactor | reactor | nuclear reactor | nuclear reactor | thermal behavior | thermal behavior | hydraulic | hydraulic | hydraulic behavior | hydraulic behavior | heat | heat | modeling | modeling | steam | steam | stability | stability | instability | instability | thermo-fluid dynamic phenomena | thermo-fluid dynamic phenomena | single-heated channel-transient analysis | single-heated channel-transient analysis | Multiple-heated channels | Multiple-heated channels | Loop analysis | Loop analysis | single and two-phase natural circulation | single and two-phase natural circulation | Kinematics | Kinematics | two-phase flows | two-phase flows | subchannel analysis | subchannel analysis | Core thermal analysis | Core thermal analysis

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see http://ocw.mit.edu/terms/index.htm

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22.313 Thermal Hydraulics in Nuclear Power Technology (MIT)

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

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see https://ocw.mit.edu/terms/index.htm

Site sourced from

https://ocw.mit.edu/rss/all/mit-allarchivedcourses.xml

Attribution

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22.313 Thermal Hydraulics in Nuclear Power Technology (MIT)

Description

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. Core thermal analysis approaches.

Subjects

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 | Subchannel analysis. Core thermal analysis

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see https://ocw.mit.edu/terms/index.htm

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https://ocw.mit.edu/rss/all/mit-allarchivedcourses.xml

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22.313J Thermal Hydraulics in Power Technology (MIT)

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.

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

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see https://ocw.mit.edu/terms/index.htm

Site sourced from

https://ocw.mit.edu/rss/all/mit-allcourses.xml

Attribution

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