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Applied Reactor PhysicsSecond Editi on

AUTEURS ALAIN HÉBERT

COLLECTION CURSUS

PARUTION MARS 2016

PAGES 406

FORMAT 17,15 X 24,75 CM

AUTRES 96 FIGURES ET ILLUSTRATIONS, NOMBREUX TABLEAUX ET EXERCICES

PAPIER COUVERTURE ALLEMANDE ISBN 978-2-553-01698-1

SUBJECT TREATMENTReactor physics is the discipline devoted to the study of interacti onsbetween neutrons and matt er in a nuclear reactor. In Applied ReactorPhysics, reactor physics is approached from the fundamental level.Legacy numerical techniques are introduced with suffi cient detailsto permit their implementati on in Matlab. More advanced and/orproprietary techniques may be available in a producti on environment,but these can be obtained as evoluti ons of the fundamental approachespresented in the book.

A characteristi c of Applied Reactor Physics is to emphasize thealgorithmic nature of numerical soluti on techniques used in reactorphysics. Many numerical soluti on approaches described in the bookare accompanied by Matlab scripts and readers are encouragedto write short Matlab scripts of their own in order to solve the Endof-Chapter exercises.

TARGET AUDIENCEThis book is dedicated to an audience at the graduate level, withoutpreliminary knowledge of reactor physics. It was initi ally writt en assupport for graduate-level courses off ered in the regular program of the Insti tut de génie nucléaire at École Polytechnique de Montréal.Enough material is included for constructi ng three or four graduate courses.

AUTHORAlain Hébert has been a professor of the Insti tut de génie nucléaireat École Polytechnique de Montréal since 1981. From 1995 to 2001,he worked at the Commissariat à l’Énergie Atomique, located in Saclay, France. During this period, he led the development team ofthe APOLLO2 latti ce code, an important component of the Science™and Arcadia™ packages at Areva. Back in Montréal, he parti cipatedin the development of the DRAGON latti ce and TRIVAC reactor codes,both available as Open Source soft ware.

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Foreword

Chapter 1 Introduction

Chapter 2 Cross sections and nuclear dataSolid angles and spherical harmonics. Dealing with distributions. Dynamics of a scattering reaction. Definition of a cross section. Formation of a compound nucleus. Thermal agitation of nuclides and binding effects. Expansion of the differential cross sections. Calculation of the probability tables. Production of an isotopic cross-section library. Exercises.

Chapter 3 The transport equationThe particle flux. Derivation of the transport equation. Source density in reactor physics. The transport correction. Multigroup discretization. The first-order streaming operator. The spherical harmonicsmethod. The collision probability method. The discrete ordinatesmethod. The method of characteristics. The multigroupMonte Carlomethod. Exercises.

Chapter 4 Elements of lattice calculationA historical overview. Neutron slowing-down and resonance self-shielding. The neutron leakage model. The SPH equivalence technique. Isotopic depletion. Creation of the reactor database. A presentation of DRAGON. Exercises.

Chapter 5 Full-core calculationsThe steady-state diffusion equation. Discretization of the neutron diffusion equation. Generalized perturbation theory. Space-time kinetics. Exercises.

Answers to Problems

Appendix A Tracking of 1D and 2D geometriesAppendix B Special functions with MatlabAppendix C Numerical methods

Bibliography

Index

Applied Reactor PhysicsSecond Edition

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