Wärmeübergang in Kernreaktoren

  • Typ: Vorlesung (V)
  • Lehrstuhl: KIT-Fakultäten - KIT-Fakultät für Maschinenbau - Institut für Angewandte Thermofluidik
    KIT-Fakultäten - KIT-Fakultät für Maschinenbau
  • Semester: WS 23/24
  • Dozent: Prof. Dr.-Ing. Xu Cheng
  • SWS: 2
  • LVNr.: 2189907
  • Hinweis: Präsenz/Online gemischt

This lecture is designed for students of mechanical engineering and other engineering disciplines in their Bachelor or Master studies. The students will understand the most important heat transfer processes and learn the methods for the analysis of flow and heat transfer in nuclear reactors. Students are capable of explaining the thermal-hydraulic processes occurring in nuclear reactors and of selecting suitable models or simulation codes for thermal-hydraulic design and analysis.

  1. Reactor types and thermal-hydraulic design criteria
  2. Heat transfer processes and modeling
  3. Pressure drop calculation
  4. Temperature distribution in nuclear reactor
  5. Numerical analysis methods for nuclear reactor thermal-hydraulics
  1. L.S. Tong, J. Weisman, Thermal-hydraulics of pressurized water reactors, American Nuclear Society, La Grande Park, Illinois, USA
  2. R.T. Lahey, F.J. Moody, The Thermal-Hydraulics of a Boiling Water Nuclear Reactor, 2nd edition, ANS, La Grande Park, Illinois, USA, 1993

This compact English lecture will be given on February 19 - 21, 2023, 09:00-17:00.

in seminar room of the Institute IATF, Building 07.08, Room 331