Thermohydraulics 1100-TERM
The detailed scope of the material covered in each session will be sent to registered students.
Term 2024L:
Day 1 Day2 Day 3 This class provides the fundamental knowledge on how to solve the governing equations employed in the nuclear thermal hydraulics analysis. It begins with an introduction of the governing equations, expressed as partial differential equations, used in the safety and performance analysis codes. The numerical methods include discretization of the partial differential operators and solution schemes of the discretized linear equations. The finite difference method (FDM) and finite volume method (FVM) will be explained for the discretization of the governing equations. Different solution schemes are introduced for single- and two-phase flow applications. For the two-phase flow, phase coupling schemes are discussed to deal with the interfacial mass, momentum and energy transfers. To enhance understanding, numerical experiments are provided for simple one-dimensional (1D) and two-dimensional (2D) conceptual problems. Day 4 Day 5 This class provides a hand on exercise of the CUPID code. There will be a CUPID user guide before the exercise, which includes description of the major input, calculation mesh input, and output processing. A CUPID executable will be available with limited approval for the class so that the students could run the CUPID code if they bring their lap top computers. A set of test problems will be provided for the exercise with the description of the problem definition and relevant input parameters. The test problem includes single/two-phase flow verifications and validations against experiments related to nuclear thermal hydraulics. |
Main fields of studies for MISMaP
Mode
Prerequisites (description)
Course coordinators
Assessment criteria
The final grade will be determined based on an exam (test) or a project.
Bibliography
The course material will be made available by the lecturers.. 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: