ADVANCED NUCLEAR REACTOR THERMAL HYDRAULICS

Course guarantor:

Lecturer:

Tomáš Dlouhý, Václav Dostál, Slavomír Entler, František Hrdlička, Jan Hrdlička, Michal Kolovratník, Pavel Zácha

Tutor:

Tomáš Dlouhý, Václav Dostál, Slavomír Entler, František Hrdlička, Jan Hrdlička, Michal Kolovratník, Pavel Zácha

Supervisor:

Department of Energy Engineering

Synopsis:

Understand the release and distribution of thermal energy in a nuclear reactor.

Master the basic disciplines of heat removal from fuel.

Energy released and its spatial distribution in the fuel element and in the core.

The design of the reactor cooling system, which includes the choice of coolant, fuel and cladding, and energy

transfer methods (conduction heat transfer in solid structures, convection and radiant heat transfer to coolant one and two phase flow and appropriate heat transfer).

Thermal Core Thermal Design Procedure.

Utilizing the thermal energy of reactor coolant to produce steam into the coolant.

Dynamics of nuclear power plants.

Advanced computational methods using the thermohydraulic package of NRC codes.

Requirements:

Syllabus of lectures:

Syllabus of tutorials:

Study Objective:

Study materials:

Todreas, Kazimi, Nuclear Systems I, Taylor and Francis, 1993

Todreas, Kazimi, Nuclear Systems II, Taylor and Francis, 1993

Patankar, Numerical Heat Transfer and Fluid Flow, Hemisphere Publishing Corporation, 1980

Note:

Time-table for winter semester 2024/2025:

Time-table is not available yet

Time-table for summer semester 2024/2025:

Time-table is not available yet

The course is a part of the following study plans: