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CZECH TECHNICAL UNIVERSITY IN PRAGUE
STUDY PLANS
2024/2025

ADVANCED NUCLEAR REACTOR THERMAL HYDRAULICS

The course is not on the list Without time-table
Code Completion Credits Range
W15OZ007 ZK 65P+13C
Garant předmětu:
Lecturer:
Tutor:
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:
Further information:
No time-table has been prepared for this course
The course is a part of the following study plans:
Data valid to 2024-05-29
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