Completed undergraduate (first) degree.

Positive result from colloquium (or written exam) is necessary to enter the oral exam.

# Nuclear thermalhydraulics

TBasic equations of fluid mechanics, heat transfer and mass transfer. Fundamentals of thermodynamics of two-phase mixtures of water and steam.

Basic conservation equations of two-phase flow.

Two-phase flow: two-phase flow regimes. Emphasis on two-phase flows in nuclear engineering. Simple methods for analysis of two-phase flow in piping systems.

Models of two-phase flow: time and space averaged basic conservation equations for two-phase flow. Two-fluid models of two-phase flow. Heat transfer between wall and two-phase flow. Boiling in a vertical hot channel. Interphase exchange of matter and energy. Transition from single-phase to two-phase flow: boiling and cavitation in liquids, steam condensation.

Important phenomena in nuclear technology: instability of two-phase flow, critical flow, flow in steam generators, boiling crisis and critical heat flux.

Analysis of transient phenomena in piping systems.

Uncertainties of two-phase flow models.

Bird, Stewart, Lightfoot, Transport Phenomena, John Wiley & Sons, 1960.

Todreas, Kazimi, Nuclear systems. Volume I, Thermal hydraulic fundamentals, Hemisphere Publ. Comp., 1989,

Todreas, Kazimi, Nuclear systems. Volume II, Elements of thermal hydraulic design, Hemisphere Publ. Comp., 1990.

Landau, Lifshitz: "Fluid Mechanics" (Course of Theoretical Physics Vol.6) ,

Ishii, Hibiki, "Thermo-Fluid Dynamics of Two-Phase Flow", Springer, 2006.

Mills, Heat Transfer, Prentice Hall, 1999.

Objectives: Understanding and modelling of thermal-hydraulic processes in nuclear power plant systems. Familiarizing with transient phenomena in cooling systems of nuclear power plants.

Competences: Modelling and ability to solve problems; computer skills.

Knowledge and understanding:

Learn about phenomena in the fields of fluid mechanics, heat transfer and mass transfer, which are important for the operation of nuclear power plants. Emphasis on dynamics of two-phase flow, boiling, forced and natural convection, and transient phenomena in piping systems of nuclear power plants.

Application:

Ability to analyse basic thermal-hydraulic phenomena in nuclear power plants.

Reflection:

Ability to assess the quality of mathematical models of various phenomena in two-phase flow.

Transferable skills:

Familiarizing with basic conservation equations of fluid mechanics and heat transfer. Behaviour of two-phase flow of liquid water and steam in piping systems.

Lectures and exercises, homeworks. Some content will be given in the form of e-lessons, using web-based content for distance learning.

Final written exam

Oral exam

grading: 5 (fail), 6-10 (pass) (according to the Statute of UL)

Iztok Tiselj:

1. TISELJ, I, PETELIN, S. First and second order accurate schemes for two-fluid models. ASME - J. fluids eng., 1998, vol. 120 (2), str. 363-368.

2. TISELJ, Iztok, ČERNE, Gregor. Some comments on the behaviour of the RELAP5 numerical scheme at very small time steps. Nucl. sci. eng., 2000, vol. 134, str. 306-311.

Ivo Kljenak:

1. KLJENAK, I., BABIĆ, M., MAVKO, B., BAJSIĆ, I. Modeling of containment atmosphere mixing and stratification experiment using a CFD approach. Nuclear Engineering and Design, 2006, vol. 236, pp. 1682-1692

2. KLJENAK, I., MAVKO, B., Simulation of containment thermal-hydraulics in the Marviken Blowdown 16 experiment with ASTEC and CONTAIN codes. Nuclear engineering and design, 2011, vol. 241, pp. 1063-1070.

3. KLJENAK, I., DAPPER, M., DIENSTBIER, J., HERRANZ, L. E., KOCH, M.K., FONTANET, J. Thermal-hydraulic and aerosol containment phenomena modelling in ASTEC severe accident computer code. Nuclear Engineering and Design, 2010, vol. 240, pp. 656-667