Thermohydraulics 1100-TERM
The following topics will be covered in this class:
- heat generation and dissipation in nuclear reactors,
- thermal analysis of fuel rods,
- heat transfer processes and numerical modelling,
- modelling of thermal-fluid processes in a nuclear power plant,
- fundamentals of heat transfer,
- 1F flow,
- safety systems and 2F flow,
- boiling, CHF and safety aspects.
Some of the meetings will take the form of workshops, where some of the calculations will be performed using MATLAB and programmes prepared by the lecturers.
Main fields of studies for MISMaP
Mode
Course coordinators
Assessment criteria
Each module (6h) will be followed by a post-test and a short interview with the lecturer.
The final mark will be the arithmetic average of the marks obtained from the four modules.
Bibliography
The course material will be made available by the lecturers on the TEAMS platform. In addition, we recommend
1. Ackermann G. i inni, Eksploatacja elektrowni jądrowych, WNT, 1987.
2. Anglart H., Thermal-Hydraulics in Nuclear Systems, 2010.
3. Celiński Z., Strupczewski A., Podstawy energetyki jądrowej, WNT, 1984.
4. Kiełkiewicz M., Teoria reaktorów jądrowych, PWN, 1987.
5. Merritt C., Process steam systems, Willey, 2016
6. Prandtl L., Dynamika przepływów, PWN, 1956
7. Wiśniewski S., Wiśniewski T.S., Wymiana ciepła, WNT, 2000.
8. Strupczewski A., Awarie reaktorowe a bezpieczeństwo energetyki jądrowej, WNT, 1990.
Additional information
Additional information (registration calendar, class conductors, localization and schedules of classes), might be available in the USOSweb system: