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Thermo-Hydraulics of Nuclear Reactors


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Table of Contents

1. Introduction; 2. Basic nuclear power generation; 3. CORE neutronics; 4. Some reactor designs; 5. Core heat transfer; 6. Multiphase flow; 7. Reactor multiphase flows and accidents.

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This book provides a concise summary of the essential thermo-hydraulic analyses and design principles of nuclear reactors for electricity generation.

About the Author

Professor Christopher Earls Brennen was a member of the Mechanical Engineering Faculty at Caltech for over forty years and retired as the Richard L. and Dorothy M. Hayman Professor of Mechanical Engineering in 2005. As a teacher he was the recipient of a number of teaching awards including the prestigious Richard Feynman Prize.

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