Advanced Aspects of Nuclear Reactor Thermal Hydraulics Design

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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).

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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

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Further information:

No time-table has been prepared for this course

The course is a part of the following study plans: