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CZECH TECHNICAL UNIVERSITY IN PRAGUE
STUDY PLANS
2019/2020

Advanced Aspects of Nuclear Reactor Thermal Hydraulics Design

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Code Completion Credits Range
W15O009 ZK 4P+1C
Lecturer:
Václav Dostál (guarantor)
Tutor:
Václav Dostál (guarantor)
Supervisor:
Department of Energy Engineering
Synopsis:

Heat release in a nuclear reactor (effect of fuel loading patterns, heat release during transients heat release in moderator and structural materials), fuel elements and their realistic temperature profiles. Fuel pin behavior during transients. Hydrodynamics of a nuclear reactor with respect to vibration induced by flow, design of absorption elements, two phase flow modelling and behavior of pumps during two phase flow. Instability of flow and separation of steam and liquid volume. Heat transfer models, effect of spacer grids with mixing vanes, condensation models. Basics of thermal and hydraulic design of a nuclear reactor, main limiting factors. Subchannel analysis, stochastic approach to thermal design of a nuclear. Safety analysis LOCA and ATWS. System codes used for thermal hydraulic design of a nuclear reactor (RELAP, ATLET, TRACE).

Requirements:
Syllabus of lectures:
Syllabus of tutorials:
Study Objective:
Study materials:

N. E. Todreas and M. S. Kazimi, ?Nuclear Systems Volume I: Thermal Hydraulic Fundamentals, Revised 2nd ed,? CRC Press, 2015; ?Volume II: Elements of Thermal Hydraulic Design,? 2001.

Thermal Analysis of Pressurized Water Reactors 3rd Edition

by L. S. Tong (Author), Joel Weisman

Note:
Time-table for winter semester 2019/2020:
Time-table is not available yet
Time-table for summer semester 2019/2020:
Time-table is not available yet
The course is a part of the following study plans:
Data valid to 2019-09-22
For updated information see http://bilakniha.cvut.cz/en/predmet5093706.html