Applied Reactor Physics - Second edition

ISBN9782553016981 EditeurPresses internationales Polytechnique pages406 Parution2016-03-14
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Quatrième de couverture

Reactor physics is the discipline devoted to the study of interactions between neutrons and matter in a nuclear reactor. In Applied Reactor Physics, reactor physics is approached from the fundamental level. Legacy numerical techniques are introduced with sufficient details to permit their implementation in Matlab. More advanced and/or proprietary techniques may be available in a production environment, but these can be obtained as evolutions of the fundamental approaches
presented in the book. A characteristi c of Applied Reactor Physics is to emphasize the algorithmic nature of numerical solution techniques used in reactor physics. Many numerical solution approaches described in the book are accompanied by Matlab scripts and readers are encouraged to write short Matlab scripts of their own in order to solve the Endof-Chapter exercises.


This book is dedicated to an audience at the graduate level, without preliminary knowledge of reactor physics. It was initi ally writt en as support 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.
Alain Hébert has been a professor of the Insti tut de génie nucléaire at 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 of the APOLLO2 latti ce code, an important component of the Science™ and Arcadia™ packages at Areva. Back in Montréal, he parti cipated in the development of the DRAGON latti ce and TRIVAC reactor codes, both available as Open Source soft ware.
Chapter 1 Introduction
Chapter 2 Cross sections and nuclear data
Solid 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
Chapter 3 The transport equation
The 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
Chapter 4 Elements of lattice calculation
A 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
Chapter 5 Full-core calculations
The steady-state diffusion equation
Discretization of the neutron diffusion equation
Generalized perturbation theory
Space-time kinetics
Answers to Problems
Appendix A Tracking of 1D and 2D geometries
Appendix B Special functions with Matlab
Appendix C Numerical methods