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Christophe Demazière - Modelling of Nuclear Reactor Multi-physics: From Local Balance Equations to Macroscopic Models in Neutronics and Thermal-Hydraulics

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    Modelling of Nuclear Reactor Multi-physics: From Local Balance Equations to Macroscopic Models in Neutronics and Thermal-Hydraulics
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Modelling of Nuclear Reactor Multi-physics: From Local Balance Equations to Macroscopic Models in Neutronics and Thermal-Hydraulics: summary, description and annotation

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Modelling of Nuclear Reactor Multiphysics: From Local Balance Equations to Macroscopic Models in Neutronics and Thermal-Hydraulics is an accessible guide to the advanced methods used to model nuclear reactor systems. The book addresses the frontier discipline of neutronic/thermal-hydraulic modelling of nuclear reactor cores, presenting the main techniques in a generic manner and for practical reactor calculations.

The modelling of nuclear reactor systems is one of the most challenging tasks in complex system modelling, due to the many different scales and intertwined physical phenomena involved. The nuclear industry as well as the research institutes and universities heavily rely on the use of complex numerical codes. All the commercial codes are based on using different numerical tools for resolving the various physical fields, and to some extent the different scales, whereas the latest research platforms attempt to adopt a more integrated approach in resolving multiple scales and fields of physics. The book presents the main algorithms used in such codes for neutronic and thermal-hydraulic modelling, providing the details of the underlying methods, together with their assumptions and limitations. Because of the rapidly expanding use of coupled calculations for performing safety analyses, the analysists should be equally knowledgeable in all fields (i.e. neutron transport, fluid dynamics, heat transfer).

The first chapter introduces the books subject matter and explains how to use its digital resources and interactive features. The following chapter derives the governing equations for neutron transport, fluid transport, and heat transfer, so that readers not familiar with any of these fields can comprehend the book without difficulty. The book thereafter examines the peculiarities of nuclear reactor systems and provides an overview of the relevant modelling strategies. Computational methods for neutron transport, first at the cell and assembly lev

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Christophe Demazière
Modelling of Nuclear Reactor Multi-physics: From Local Balance Equations to Macroscopic Models in Neutronics and Thermal-Hydraulics

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Table of Contents
List of Figures
  1. Figures in 1
  2. Figures in 2
  3. Figures in 3
  4. Figures in 4
  5. Figures in 5
  6. Figures in 6
  7. Figures in 7
List of Tables
  1. Tables in 2
  2. Tables in 5
Landmarks
Modelling of Nuclear Reactor Multi-physics From Local Balance Equations to - photo 1
Modelling of Nuclear Reactor Multi-physics
From Local Balance Equations to Macroscopic Models in Neutronics and Thermal-Hydraulics
Christophe Demazire
Table of Contents Copyright Academic Press is an imprint of Elsevier 125 London - photo 2
Table of Contents
Copyright
Academic Press is an imprint of Elsevier
125 London Wall, London EC2Y 5AS, United Kingdom
525 B Street, Suite 1650, San Diego, CA 92101, United States
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The Boulevard, Langford Lane, Kidlington, Oxford OX5 1GB, United Kingdom
Copyright 2020 Elsevier Inc. All rights reserved.
No part of this publication may be reproduced or transmitted in any form or by any means, electronic or mechanical, including photocopying, recording, or any information storage and retrieval system, without permission in writing from the publisher. Details on how to seek permission, further information about the Publishers permissions policies and our arrangements with organizations such as the Copyright Clearance Center and the Copyright Licensing Agency, can be found at our website: www.elsevier.com/permissions.
This book and the individual contributions contained in it are protected under copyright by the Publisher (other than as may be noted herein).
Notices
Knowledge and best practice in this field are constantly changing. As new research and experience broaden our understanding, changes in research methods, professional practices, or medical treatment may become necessary.
Practitioners and researchers must always rely on their own experience and knowledge in evaluating and using any information, methods, compounds, or experiments described herein. In using such information or methods they should be mindful of their own safety and the safety of others, including parties for whom they have a professional responsibility.
To the fullest extent of the law, neither the Publisher nor the authors, contributors, or editors, assume any liability for any injury and/or damage to persons or property as a matter of products liability, negligence or otherwise, or from any use or operation of any methods, products, instructions, or ideas contained in the material herein.
Library of Congress Cataloging-in-Publication Data
A catalog record for this book is available from the Library of Congress
British Library Cataloguing-in-Publication Data
A catalogue record for this book is available from the British Library
ISBN: 978-0-12-815069-6
For information on all Academic Press publications visit our website at https://www.elsevier.com/books-and-journals
Publisher: Joe Hayton
Acquisition Editor: Maria Convey
Editorial Project Manager: Aleksandra Packowska
Production Project Manager: Sruthi Satheesh
Cover Designer: Greg Harris
Typeset by TNQ Technologies

Dedication To Anna Clara Noah and Elsa To Marcelle and Jean List of - photo 3

Dedication

To Anna, Clara, Noah and Elsa To Marcelle and Jean

List of Abbreviations
BOC Beginning of Cycle
BWR Boiling Water Reactor
CFD Computational Fluid Dynamics
CFL Courant-Friedrichs-Lewy (condition)
DSA Diffusion Synthetic Acceleration
ENDF Evaluated Nuclear Data File
EOC End of Cycle
JEF Joint Evaluated File
JEFF Joint Evaluated Fission and Fusion
JFNK Jacobian-Free Newton Krylov
FIV Flow-Induced Vibration
FSI Fluid-Structure Interaction
GMRES Generalized Minimal Residual method
HEM Homogeneous Equilibrium Model
IR Intermediate Resonance
LWR Light Water Reactor
NR Narrow Resonance
OS Operator Splitting
PWR Pressurized Water Reactor
RI Resonance Integral
RPV Reactor Pressure Vessel
SOR Successive Over Relaxation
WR Wide Resonance
Introduction
Abstract

In this introductory chapter, the main topics addressed in the book are first discussed, together with the objectives the book attempts to tackle. Areas not covered in the book are also described. The structure of the book is thereafter presented. Both the technical contents as well as the followed pedagogical approach are dealt with. The notations and conventions used throughout the book are then highlighted. Finally, some mathematical concepts and theorems of importance for the following chapters are presented.

Keywords
Fluid dynamics; Heat transfer; Multi-physics; Multi-scale; Neutron transport; Nuclear reactor modelling
1.1. Topics covered in the book
This book deals with the macroscopic modelling of nuclear reactor cores, with emphasis on neutron transport, fluid dynamics, heat transfer, and the interdependencies between these three areas of physics. Due to the complexity and large size of a nuclear reactor core, a modelling of all physical processes on all scales represents a challenge from a computational viewpoint.
Methods were thus specifically derived to simplify the problem at hand by averaging the true local balance equations onto sufficiently large meshes for each of the variables used to describe each of the physics. As a result, the corresponding methods are referred to as macroscopic approaches. Such methods, because of their moderate computing costs, are routinely used by the nuclear industry to characterize the behaviour of a core during both normal and abnormal situations not leading to core damage.
The averaging procedure used to transform the actual local balance equations into their macroscopic equivalent form is far from trivial. In addition, many approximations are introduced when performing the averaging of the local balance equations.
The purpose of the present book is to present, in a comprehensive manner, how to derive from the true local balance equations the macroscopic balance equations the modelling tools used by the nuclear industry solve. The corresponding methods and algorithms are thus thoroughly presented, together with their approximations and limitations. The primary objective with this book is to give the readers a description of such methods and algorithms, so that the readers can later use the codes based on those methods with confidence and for situations falling into the range of validity of the algorithms. The book also tackles the modelling of all physical phenomena of importance and their interdependencies. This guarantees a holistic approach to the field of nuclear reactor modelling. This is of particular importance in the area of nuclear reactor transients, where the analysts need to be equally knowledgeable in neutron transport, fluid dynamics and heat transfer.
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