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+\begin{thebibliography}{99}
+
+\bibitem{PIP2016}
+A. H\'ebert, Applied Reactor Physics, Second Edition, Presses Internationales Polytechnique, ISBN 978-2-553-01698-1, 396 p., Montr\'eal, 2016.
+
+\bibitem{v4}
+A. H\'ebert, "Development Procedures for Version4 of
+Reactor Physics Codes," Report IGE-287,
+\'Ecole Polytechnique de Montr\'eal,
+ Institut de G\'enie Nucl\'eaire (2006).
+
+\bibitem{cle2000}
+R.~Roy, ``The CLE-2000 Tool-box," 
+Report IGE-163, \'Ecole Polytechnique de Montr\'eal,
+Institut de G\'enie Nucl\'eaire (1999).
+
+\bibitem{ganlib5}
+A. H\'ebert and R.~Roy,
+``The Ganlib5 kernel guide (64--bit clean version),"
+Report IGE-332, \'Ecole Polytechnique de Montr\'eal, January 2013.
+
+\bibitem{dragon}
+G. Marleau, A. H\'ebert and R. Roy,
+"A User Guide for DRAGON Version5,"
+Report IGE-335, \'Ecole Polytechnique de Montr\'eal,
+Institut de G\'enie Nucl\'eaire (2014).
+
+\bibitem{trivac}
+A. H\'ebert, "A User Guide for TRIVAC Version4,"
+Report IGE-293, \'Ecole Polytechnique de Montr\'eal,
+Institut de G\'enie Nucl\'eaire (2007).
+
+\bibitem{ah1}
+A. H\'ebert, "TRIVAC, A Modular Diffusion Code for Fuel Management and 
+Design Applications," {\sl Nucl. J. of Canada}, Vol. 1, No. 4, 325 (1987).
+
+\bibitem{ah2}
+A. H\'ebert, "Application of the Hermite Method for Finite Element 
+Reactor Calculations," {\sl Nucl. Sci. Eng.}, {\bf 91}, 34 (1985).
+
+\bibitem{ah3}
+A. H\'ebert, "Variational Principles and Convergence Acceleration 
+Strategies for the Neutron Diffusion Equation," {\sl Nucl. Sci. Eng.}, 
+{\bf 91}, 414 (1985).
+
+\bibitem{ah4}
+A. H\'ebert, "Preconditioning the Power Method for Reactor Calculations,"
+{\sl Nucl. Sci. Eng.}, {\bf 94}, 1 (1986).
+
+\bibitem{ah5}
+A. H\'ebert, "Development of the Nodal Collocation Method for Solving 
+the Neutron Diffusion Equation," {\sl Ann. Nucl. Energy}, {\bf 14}, 
+527 (1987).
+
+\bibitem{ah6}
+A. H\'ebert, "Application of a Dual Variational Formulation to Finite 
+Element Reactor Calculations," {\sl Ann. nucl. Energy}, {\bf 20}, 823 (1993).
+
+\bibitem{donjon}
+E. Varin,  A. H\'ebert, J. Koclas and R. Roy, "A User Guide for DONJON,"
+Report IGE-208, , \'Ecole Polytechnique de Montr\'eal,
+Institut de G\'enie Nucl\'eaire (2005).
+
+\bibitem{donjstruc}
+E. Varin, A. H\'ebert,
+"Data Structures for DONJON," 
+Report IGE-226, \'Ecole Polytechnique de Montr\'eal,
+ Institut de G\'enie Nucl\'eaire (2003).
+
+\bibitem{rozon}
+D. Rozon, 
+"Gestion du combustible nucl\'eaire. Notes de cours Ene6109,"
+Report IGE-298, \'Ecole Polytechnique de Montr\'eal,
+ Institut de G\'enie Nucl\'eaire (2007).
+
+\bibitem{chambon}
+R. Chambon,
+{\sl Optimisation de la gestion du combustible dans les r\'eacteurs
+CANDU refroidis \`a l'eau l\'eg\`ere}, Ph. D. Thesis, \'Ecole Polytechnique de Montr\'eal (2006). 
+
+\bibitem{Intech2011}
+A. H\'ebert, {\sl Revisiting the Ceschino Interpolation Method}, in {\sl MATLAB -- A Ubiquitous Tool for the Practical
+Engineer}, Clara M. Ionescu (Ed.), InTech Open Access Publisher, ISBN 978-953-307-907-3, Croatia, 2011.
+
+\bibitem{dragstruc}
+A. H\'ebert, G. Marleau and R. Roy, 
+"A description of the DRAGON Data Structures," 
+Report IGE-295, \'Ecole Polytechnique de Montr\'eal,
+ Institut de G\'enie Nucl\'eaire (2007).
+
+\bibitem{hst}
+E. Varin and G. Marleau, ``CANDU reactor core simulations using fully coupled DRAGON and DONJON calculations,"
+{\sl Ann. Nucl. Energy}, {\bf 33}, 682 (2006).
+
+\bibitem{tajmouati}
+J. Tajmouati, ``Optimisation de la gestion du combustible enrichi d'un r\'eacteur CANDU
+avec prise en compte des param\`etres locaux," Ph. D. thesis, \'Ecole Polytechnique de
+Montr\'eal (1993).
+
+\bibitem{sissaoui}
+M. T. Sissaoui, G. Marleau and D. Rozon, ``CANDU Reactor Simulations Using the
+Feedback Model with Actinide Burnup History," {\sl Nucl. Technology}, {\bf 125},
+197 (1999).
+
+\bibitem{anl}
+"Argonne Code Center: Benchmark Problem Book," ANL-7416, Supp. 2, ID11-A2, 
+Argonne National Laboratory (1977).
+
+\bibitem{apollo2}
+S. Loubi\`ere, R. Sanchez, M. Coste, {\bf A. H\'ebert}, Z. Stankovski, C. Van Der Gucht and I. Zmijarevic, ``APOLLO2,
+Twelve Years Later," paper presented at the {\sl Int. Conf. on Mathematics and Computation,
+Reactor Physics and Environmental Analysis in Nuclear Applications}, Madrid, Spain, September 27--30, 1999.
+
+\bibitem{apollo2A}
+A. Janet, ``APOLLO2-A User's Manual Version 1.26.0," Report D02-DTIPD-F-17-0503, CONV17\_0026, Framatome (2018).
+
+\bibitem{apollo3}
+I. Zmijarevic, N. Huot, F. Auffret and P. Bellier, ``Description of the APOLLO3 Multi-parameter Output Library for the
+version AP3-2.0,'' DEN/DANS/DM2S/SERMA/LTSD/RT/17-6237/A, Commissariat \`a l'\'energie atomique et aux \'energies alternatives (2017).
+
+\bibitem{Griffiths94}
+J.~Griffiths,  
+\textsl{WIMS--AECL Users Manual},
+Report RC-1176, Atomic Energy of Canada Limited, Chalk River, Ontario (1994).
+
+\bibitem{Donnelly97a}
+J.V.~Donnelly,  
+\textsl{Post-Processing WIMS-AECL Results with Proc16},
+Report FCC-RCP-001, Atomic Energy of Canada Limited, Chalk River, Ontario (1997).
+
+\bibitem{Donnelly97c}
+J.V.~Donnelly,  
+\textsl{Wrfsp: Post-Processing Data from WIMS-AECL to RFSP},
+Report FCC-RCP-006, Atomic Energy of Canada Limited, Chalk River, Ontario (1997).
+
+\bibitem{freesteam}
+See the home page at \url{http://freesteam.sourceforge.net/}.
+
+\bibitem{optex1}
+D. Rozon, A. H\'ebert and D. McNabb, ``The application of generalized perturbation theory and mathematical programming
+to equilibrium refueling studies of a CANDU reactor," {\sl Nucl.Sci. Eng.}, {\bf 78}, 211 (1981).
+
+\bibitem{optex2}
+R. Chambon, E. Varin and D. Rozon, ``CANDU fuel management optimization using alternative gradient
+methods," {\sl Ann. Nucl. Energy}, {\bf 34}, 1002 (2007).
+
+\bibitem{optex3}
+A. H\'ebert and H. Leroyer, ``A Presentation of the OPTEX Reflector Model," {\sl Nucl. Sci. Eng.},  {\bf 176}, 312--324 (2014).
+
+\bibitem{recipie}
+W.~H.~Press, B.~P.~Flannery, S.~A.~Teukolsky and W.~T.~Vetterling, {\sl Numerical Recipes in FORTRAN, Second Edition}, Cambridge University Press, Cambridge (1992).
+
+\bibitem{armijo}
+L. Armijo, ``Minimization of functions having Lipschitz continuous
+first partial derivatives," {\sl Pacific journal of mathematics}, Vol. 16,
+{\bf 1}, 1--3, 1966.
+
+\bibitem{nocedal}
+J. Nocedal, ``Updating Quasi-Newton Matrices With Limited Storage," {\sl Math. of Computation}, Vol. 35, {\bf 151}, 773--782 (1980).
+
+\bibitem{sph1981}
+A. H\'ebert, ``D\'eveloppement de la m\'ethode SPH: Homog\'en\'eisation de cellules dans un r\'eseau non uniforme et calcul des param\`etres de r\'eflecteur," Ph. D. thesis, CEA-N-2209 (1981).
+
+\bibitem{sph2019}
+A. H\'ebert, ``A general presentation of the SPH equivalence technique in non-fundamental mode cases," Submitted to {\sl Annals of Nucl. Energy} (2019).
+
+\bibitem{inl}
+V. Labour\'e, Y. Wang, J. Ortensi, S. Schunert, F. Gleicher, M. DeHart and R. Martineau, ``Hybrid super homogenization and discontinuity factor method for continuous finite element diffusion," {\sl Ann. nucl. Energy}, {\bf 128}, 443--454 (2019).
+
+\bibitem{mixte-dual}
+A. H\'ebert, ``Application of a Dual Variational Formulation to Finite Element Reactor Calculations'', {\sl Ann. nucl. Energy}, {\bf 20}, 823 - 845 (1993).
+
+\bibitem{ane10a}
+A. H\'ebert, ``Mixed-dual implementations of the of the simplified $P_n$ method," {\sl Ann. nucl. Energy}, {\bf 37}, 498--511 (2010).
+
+\bibitem{ferland}
+J. A. Ferland, ``A linear programming problem with an additional
+quadratic constraint solved by parametric linear complementarity,"
+Publication number 497, D\'epartement d'informatique et de recherche
+op\'erationnelle, Universit\'e de Montr\'eal, January 1984.
+
+\bibitem{fehri} M. F. Fehri, ``D\'eveloppement d'un code de thermohydraulique pour le couplage neutro\-nique/thermohydraulique,"
+M. Sc. A. Thesis, \'Ecole Polytechnique de Montr\'eal (2008).
+
+\bibitem{gallet} P. Gallet, ``D\'eveloppement d'un module de thermohydraulique simplifi\'ee dans le code DONJON4 pour l'\'etude multiphysique
+des r\'eacteurs \`a eau pressuris\'ee," Ph. D. Thesis, \'Ecole Polytechnique de Montr\'eal (2014).
+
+\bibitem{bowring}
+R. W. Bowring, "Physical Model, Based on Bubble Detachment, and Calculation of Steam Voidage in the Subcooled
+Region of a Heated Channel," OECD Report HPR-10, 1962.
+
+\bibitem{saha-zuber}
+P. Saha and N. Zuber, ``Point Of Net Vapor Generation and Vapor Void Fraction in Subcooled Boiling," {\sl Int. heat transfer conference}, Tokyo, Japan, 3 Sep 1974.
+
+\bibitem{lahey}
+R. T. Lahey and F. J. Moody, {\sl The Thermal-Hydraulics of a Boiling Water Nuclear Reactor},
+American Nuclear Society Publications, U.S.A. (1977).
+
+\bibitem{Chambon2014}
+R. Chambon, ``Specifications and User Guide for {\tt NAP:} module in DRAGON/DONJON VERSION5
+(Pin Power Reconstruction module)," Report IGE-345,
+\'Ecole Polytechnique de Montr\'eal,
+ Institut de G\'enie Nucl\'eaire (2014).
+
+\bibitem{Fliscounakis2011}
+M. Fliscounakis, E. Girardi and T. Courau, ``A Generalized Pin-Power Reconstruction Method for
+Arbitrary Heterogeneous Geometries," M\&C 2011, Rio de Janero, Brasil, May 8--12 2011.
+
+\bibitem{Rowlands}
+G. Rowlands, ``Resonance Absorption and Non-Uniform Temperature Distributions," Journal of
+Nuclear Energy Parts A/B, 16, pp 235-236 (1962).
+
+\bibitem{PARCS}
+T. Downar, Y. Xu and V. Seker, ``PARCS v3.0, U.S. NRC Core Neutronics Simulator, User Manual," Department of Nuclear Engineering and Radiological Science, University of Michigan, Ann Arbor, MI (2012).
+
+\bibitem{GENPMAXS}
+A. Ward, Y. Xu and T. Downar, ``GenPMAXS--v6.1.1, Code for Generating the PARCS Cross Section Interface File PMAXS," University of Michigan, 2013.
+
+\end{thebibliography}