From 7dfcc480ba1e19bd3232349fc733caef94034292 Mon Sep 17 00:00:00 2001
From: stainer_t <thomas.stainer@oecd-nea.org>
Date: Mon, 8 Sep 2025 13:48:49 +0200
Subject: Initial commit from Polytechnique Montreal

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+\begin{thebibliography}{99}
+
+\bibitem{PIP2009}
+A. H\'ebert, {\sl Applied Reactor Physics}, Second Edition, Presses Internationales Polytechnique, ISBN 978-2-553-01698-1, 396 p., Montr\'eal, 2016.
+
+\bibitem{Dragon1}
+G. Marleau and A. H\'ebert, ``A New Driver for Collision Probability Transport
+Codes", {\sl Int. Top. Mtg. on Advances in Nuclear Engineering
+Computation and Radiation Shielding}, Santa Fe, New Mexico, April 9--13 (1989).
+
+\bibitem{Dragon2}
+G.~Marleau, R.~Roy and A.~H\'{e}bert,
+``DRAGON: A Collision Probability Transport Code for Cell and Supercell
+Calculations'',  Report IGE--157,  \'{E}cole Polytechnique de Montr\'{e}al
+(1993).
+
+\bibitem{Dragon3}
+G.~Marleau, A.~H\'{e}bert and R.~Roy, ``New Computational Methods Used in
+the Lattice Code DRAGON'',  {\sl Top Mtg. on Advances in Reactor Physics},
+Charleston, SC, March 8-11 1992; 
+
+\bibitem{Dragon4}
+A.~H\'{e}bert, G.~Marleau and R.~Roy, ``Application of the Lattice Code
+DRAGON to CANDU Analysis'',  {\sl Trans. Am. Nucl. Soc.}, {\bf 72}, 335 (1995);
+
+\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{cle2000}
+R.~Roy, \textsl{The CLE-2000 Tool-Box}, 
+Report IGE--163, Institut de g\'enie nucl\'eaire, \'{E}cole Polytechnique de Montr\'eal,
+Montr\'{e}al, Qu\'{e}bec (1999).
+
+\bibitem{Apollo}
+A.~Hoffman et al., ``APOLLO: Code Multigroupe de r\'esolution de l'\'equation du
+transport pour les neutrons  thermiques et rapides'', CEA-N-1610, Commisariat
+\`a l'\'Energie Atomique, France (1973).
+
+\bibitem{Apollo2}
+S. Loubi\`ere, R. Sanchez, M. Coste, A. H\'ebert, Z. Stankovski, C. Van Der Gucht and I. Zmijarevic, ``APOLLO2,
+Twelve Years Later", {\sl Int. Conf. on Mathematics and Computation,
+Reactor Physics and Environmental Analysis in Nuclear Applications}, Madrid, Spain, September 27--30, 1999.
+
+\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{ndas}
+P. J. Laughton, ``NJOYPREP and WILMAPREP: UNIX-Based Tools for WIMS-
+AECL Cross-Section Library Production," Atomic Energy of Canada,
+Report COG-92-414 (Rev. 0), June 1993.
+
+\bibitem{subg}
+A.~H\'ebert, ``A Comparison of Three Techniques for Computing Probability
+Tables", {\sl Int. Conf. on the Physics of Nuclear Science and Technology},
+Long Island, New York, October 5 -- 8, 1998.
+
+\bibitem{pt}
+A.~H\'ebert and M.~Coste, ``Computing Moment-Based Probability Tables for
+Self-Shielding Calculations in Lattice Codes," {\sl Nucl. Sci. Eng.}, {\bf 142},
+245 - 257 (2002).
+
+\bibitem{nse2004}
+A.~H\'ebert, ``The Ribon Extended Self-Shielding Model," {\sl Nucl. Sci. Eng.}, {\bf 151}, 1-24  (2005).
+
+\bibitem{SPM09}
+A. H\'ebert, ``Development of the Subgroup Projection Method for Resonance Self-Shielding Calculations," {\sl Nucl. Sci. Eng.} {\bf 162}, 56-75 (2009).
+
+\bibitem{rse2021}
+R. Kondo, T. Endo, A. Yamamoto, S. Takeda, H. Koike, K. Yamaji and D. Sato, ``A New Resonance Calculation Method Using Energy
+Expansion Based on a Reduced Order Model," {\sl Nucl. Sci. Eng.} {\bf 195}, 694-716 (2021).
+
+\bibitem{wlup}
+B. Dodd, S. Basu, S. Paranjpe and A. Trkov, ``WIMS-D Library Update," International Atomic Energy Agency
+Report STI/PUB/1264, Vienna, Austria (2007).
+
+\bibitem{st}
+M.~Coste {\sl et al}, ``New Improvements in the Self-Shielding Formalism of the APOLLO2
+Code", {\sl Joint Int. Conf. on
+Mathematical Methods and Supercomputing in Nuclear Applications}, Karlsruhe,
+Germany, April 19 -- 23, 1993.
+
+\bibitem{SPH}
+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'', CEA-N-2209, Commissariat \`a l'\'Energie Atomique, France (1981).
+
+\bibitem{roy}
+R.~Roy, D.~Rozon, A.~H\'ebert and G.~Hotte, `` Treatment of Circular Boundary
+Conditions in Neutron Diffusion Calculations", Third Int. Conf. on Simulation
+Methods in Nuclear Engineering, Montr\'eal, Canada, April 18 -- 20,
+1990.
+
+\bibitem{DragonPIJI}
+R.~Roy, A.~H\'ebert and G.~Marleau, ``A Transport Method for Treating
+Three-Dimensional Lattices of Heterogeneous Cells", {\sl Nucl.~Sci.~Eng.}, {\bf
+101}, 217 (1989).
+
+\bibitem{Mtl93a}
+ R.~Roy, G.~Marleau, J.~Tajmouati and D.~Rozon, ``Modelling of CANDU Reactivity
+Control Devices with the Lattice Code DRAGON'', {\sl Ann.~nucl.~Energy}, {\bf
+21}, 115 (1994).
+
+\bibitem{mccg}
+I.~R.~Suslov, ``Solution of Transport Equation in 2-- and 3--Dimensional
+Irregular Geometry by the Method of Characteristics", {\sl Joint Int. Conf. on
+Mathematical Methods and Supercomputing in Nuclear Applications}, Karlsruhe,
+Germany, April 19 -- 23, 1993.
+
+\bibitem{suslov2}
+I. R. Suslov, ``An Algebraic Collapsing Acceleration Method for Acceleration of the Inner (Scattering) Iterations in Long Characteristics Transport Theory",
+{\sl Int. Conf. on Supercomputing in Nuclear Applications}, Paris, France, September 22 -- 24, 2003.
+
+\bibitem{chicago2}
+R. Le Tellier and A. H\'ebert, ``Application of the DSA Preconditioned GMRES Formalism to the Method of Characteristics -- First Results",
+{\sl Int. Mtg. on the Physics of Fuel Cycles and Advanced Nuclear Systems:
+Global Developments. PHYSOR-2004}, Chicago, Illinois, April 25 -- 29, 2004.
+
+\bibitem{DragonPIJS1}
+R.~Roy, ``Anisotropic Scattering for Integral Transport Codes. Part 1. Slab
+Assemblies", {\sl Ann.~nucl.~Energy}, {\bf 17}, 379 (1990).
+
+\bibitem{DragonPIJS2}
+R.~Roy, ``Anisotropic Scattering for Integral Transport Codes. Part 2. Cyclic
+Tracking and its Application to $XY$ Lattices" {\sl Ann.~nucl.~Energy}, {\bf
+18}, 511 (1991).
+
+\bibitem{DragonPIJS3}
+R.~Roy, G.~Marleau, A.~H\'ebert and D. Rozon, ``A Cyclic Tracking Procedure for Collision
+Probability Calculations in 2-D Lattices'', {\sl Int. Topical Meeting on
+Advances in Mathematica, Computation and Reactor Physics}, Pittsburgh, PA, April
+28 -- May 2, 1991. 
+
+\bibitem{Mtl93b} 
+G.~Marleau and R.~Roy, ``Use of Specular Boundary Conditions for CANDU Cell
+Analysis'',  {\sl Fourth Int. Conf. on Simulation Methods in Nuclear
+Engineering}, Montr\'eal, June 2-4, 1993.
+
+\bibitem{cdd}
+H.~Khalil, ``Effectiveness of a Consistently Formulated Diffusion Synthetic
+Acceleration Differencing approach", {\sl Nucl.~Sci.~Eng.}, {\bf 98}, 226 (1988).
+
+\bibitem{kba}
+K. Koch, R. Baker, and R. Alcouffe, ``Solution of the First-Order Form of the Three-Dimensional Discrete Ordinates Equation on
+a Massively Parallel Machine,'' {\sl Trans. Am. Nucl. Soc.}, {\bf 65}, 198 (1992). 
+
+\bibitem{domino}
+S. Moustafa, I. Dutka-Malen, L. Plagne, A. Pon\c cot and P. Ramet, ``Shared memory parallelism for 3D Cartesian discrete ordinates solver," {\sl Ann.~nucl.~Energy}, {\bf 82}, 179 (2015).
+
+\bibitem{ligou}
+K. Przybylski and J. Ligou, ``Numerical Analysis of the Boltzmann Equation Including Fokker-Planck Terms," {\sl Nucl.~Sci.~Eng.}, {\bf 81}, 92 (1982).
+
+\bibitem{gmres}
+Y. Saad and M. H. Schultz, ``GMRES: A Generalized Minimal RESidual Algorithm For Solving Nonsymmetric Linear Systems", {\sl SIAM J. Sci. Stat. Comput.}, {\bf 7}, 856-869 (1986).
+
+\bibitem{quadrupole}
+E. M. Baker, ``Quadruple range quadrature verification and extension," Los Alamos National Laboratory,
+Report LA--UR--07--8050, September 2006.
+
+\bibitem{PIM}
+G. Marleau and A. H\'ebert, ``Solving the Multigroup Transport Equation Using the
+Power Iteration Method'',  {\sl 1985 Simulation Symposium on Reactor Dynamics and
+Plant Control}, Kingston,  Ontario, April 22-23, 1985.
+
+\bibitem{Buck}
+G. Marleau and A. H\'ebert, ``Introduction of an Improved Critical Buckling
+Search in WIMS'', {\sl 1986 Simulation Symposium on Reactor Dynamics and Plant
+Control}, Hamilton, Ontario, April 21- 22, 1986.
+
+\bibitem{MATXS}
+R.E.~Macfarlane, ``TRANSX-CTR: A code for Interfacing MATXS Cross-Section
+Libraries to Nuclear  Transport Codes for Fusion Systems Analysis'', LA-9863-MS,
+Los Alamos Scientific Laboratory, New  Mexico (1984).
+
+\bibitem{WIMS}
+J.V.~Donnelly, ``WIMS-CRNL, A User's Manual for the Chalk River Version of
+WIMS'', AECL-8955,  Atomic Energy of Canada Limited (1986).
+
+\bibitem{WIMS-D}
+J.R.~Askew et al., ``A General Description of the Lattice Code WIMS'', {\sl J. of British Nucl. Energy Soc.}, {\bf 5}, 564 (1966).
+
+\bibitem{TRANSX2}
+R.E.~Macfarlane, ``TRANSX-2: A Code for Interfacing MATXS Cross-Section
+Libraries to Nuclear Transport Codes'', LA-12312-MS, Los Alamos Scientific
+Laboratory, New  Mexico (1992).
+
+\bibitem{DragonDataStructures}
+A. H\'ebert, G.~Marleau and R.~Roy,
+``A Description of the DRAGON and TRIVAC Version4 Data Structures,"
+Report IGE-295, \'Ecole Polytechnique de Montr\'eal, August 2006.
+
+\bibitem{ige260}
+G. Marleau, ``New Geometries Processing in DRAGON: The NXT: Module," Technical Report IGE-260, \'Ecole 
+Polytechnique de Montr\'eal (2006).
+
+\bibitem{eqn}
+B. G. Carlson, ``Tables of Equal Weight Quadrature $EQ_{n}$ Over the Unit Sphere," Technical Report LA-4734, 
+Los Alamos Scientific Laboratory (1971).
+
+\bibitem{pntn}
+G. Longoni, and A. Haghighat, ``Development of New Quadrature Sets with the ``Ordinate Splitting" Technique,"
+M\&C-2001, American Nuclear Society Topical Meeting in Mathematics and Computations, Salt 
+Lake City, Utah (2001), (Proceedings available on CD-Rom). 
+
+\bibitem{sms}
+R. Sanchez, L. Mao, and S. Santandrea, ``Treatment of Boundary Conditions in Trajectory-Based Deterministic
+Transport Methods," {\sl Nucl. Sci. Eng.}, {\bf 140}, 23--50 (2002). 
+
+\bibitem{RoyMoc1}
+R.~Roy, 
+``The Cyclic Characteristics Method'', 
+{\sl IInt. Conf. on the Physics of Nuclear Science and Technology}, 
+Long Island, New York, October 5--8, 1998,
+
+\bibitem{RoyMoc2}
+R.~Roy, 
+``The Cyclic Characteristics Method with Anisotropic Scattering'', 
+\textsl{M\& C'99 Mathematics and Computation, Reactor Physics and Environmental Analysis
+in Nuclear Applications}, Madrid, Spain, September  27--30, 1999,
+
+\bibitem{LCMD}
+A. Leonard and C. T. McDaniel, ``Optimal Polar Angles and Weights for the
+Characteristics Method," \textsl{Trans. Am. Nucl. Soc.}, \textbf{73}, 172 (1995).
+
+\bibitem{LeTellierpa}
+R. Le Tellier and A. H\'ebert, ``Anisotropy and Particle Conservation for Trajectory--Based 
+Deterministic Methods," {\sl Nucl. Sci. Eng.}, {\bf 158}, 28--39 (2008).
+
+\bibitem{CACTUS}
+M.J.~Halsall, 
+\textsl{CACTUS, A Characteristics Solution to the Neutron Transport 
+Equation in Complicated Geometries}, 
+Report AEEW-R 1291, Atomic Energy Establishment,
+Winfrith (1980).
+
+\bibitem{sapo}
+R. Sanchez, ``Renormalized Treatment of the Double Heterogeneity with
+the Method of Characteristics,"
+{\sl Int. Mtg. on the Physics of Fuel Cycles and Advanced Nuclear Systems:
+Global Developments. PHYSOR-2004}, Chicago, Illinois, April 25 -- 29, 2004.
+
+\bibitem{BIHET}
+A.~H\'ebert, ``A Collision Probability Analysis of the Double-Heterogeneity
+Problem", {\sl Nucl.~Sci.~Eng.}, {\bf 115}, 177 (1993).
+
+\bibitem{She2017}
+D.~She, Z.~Liu and L.~Shi, ``An Equivalent Homogenization Method for Treating the Stochastic Media", 
+{\sl Nucl.~Sci.~Eng.}, {\bf 185}, 351 (2017).
+
+\bibitem{apollo1}
+A.~Hoffmann, F.~Jeanpierre, A.~Kavenoky, M. Livolant and H. Lorain,
+``APOLLO: Code Multigroupe de R\'esolution de l'\'Equation du Transport
+pour les Neutrons Thermiques et Rapides'', Note CEA-N-1610, Commissariat
+\`a l'\'Energie Atomique, Saclay, France (1973).
+
+\bibitem{ALCOL}
+A.~Kavenoky, ``Calcul et utilisation des probabilit\'es de premi\`ere collision
+pour les milieux h\'et\'erog\`enes \`a  une dimension'', CEA-N-1077,
+Commissariat \`a l'\'Energie Atomique, France (1969).
+
+\bibitem{SANCHEZ}
+R.~Sanchez, ``Quelques sch\'emas approximatifs dans la r\'esolution
+par la m\'ethode des probabilit\'es de collision de l'\'equation
+int\'egrale du transport \`a deux dimensions'', CEA-N-2165,
+Commissariat \`a l'\'Energie Atomique, France (1980).
+
+\bibitem{BIVAC}
+A.~H\'ebert, ``Application of a Dual Variational Formulation to Finite Element
+Reactor Calculations", {\sl Ann.~nucl.~Energy}, {\bf 20}, 823 (1993).
+
+\bibitem{TRIVAC}
+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{nse2005}
+A. H\'ebert, ``The Search for Superconvergence in Spherical Harmonics Approximations,'' {\sl Nucl. Sci. Eng.}, {\bf 154}, 134 (2006).
+
+\bibitem{ane10a}
+A. H\'ebert, ``Mixed-dual implementations of the of the simplified $P_n$ method," {\sl Ann. nucl. Energy}, {\bf 37}, 498 (2010).
+
+\bibitem{SHIBA}
+A.~H\'ebert and G.~Marleau, ``Generalization of the Stamm'ler Method for the
+Self-Shielding of Resonant Isotopes in Arbitrary Geometries," {\sl
+Nucl.~Sci.~Eng.}, {\bf 108}, 230 (1991).
+
+\bibitem{njoy2010}
+R. E. MacFarlane and A. C. Kahler, ``Methods for Processing ENDF/B-VII with NJOY," {\sl Nuclear Data Sheets}, {\bf 111}, 2739 (2010).
+
+\bibitem{tone}
+T. Tone, ``A Numerical Study of Heterogeneity Effects in Fast Reactor Critical Assemblies," {\sl J. Nucl. Sci. Technol.}, {\bf 12[8]}, 467 (1975).
+
+\bibitem{toronto04}
+A.~H\'ebert, ``Revisiting the Stamm'ler Self-Shielding Method," paper presented at the
+\textsl{25th CNS Annual Conference}, June 6--9, Toronto, 2004.
+
+\bibitem{hasan}
+H.~Saygin and  A.~H\'ebert, ``A New Self-Shielding Method Based on a Detailed
+Cross-Section Representation in the Resolved Energy Domain,"
+{\sl Nucl.~Sci.~Eng.}, {\bf 122}, 276 (1996).
+
+\bibitem{coste}
+M.~Coste, ``Absorption r\'esonnante des noyaux lourds dans les
+r\'eseaux h\'et\'erog\`enes -- I-Formalisme du module
+d'autoprotection d'APOLLO2,"
+CEA-N-2746, Commissariat \`a l'\'Energie Atomique, France (1994).
+
+\bibitem{RENOR}
+R.~Roy and G.~Marleau, ``Normalization Techniques for Collision Probability
+Matrices'', {\sl PHYSOR-90}, Marseille, France, April 23--27, 1990.
+
+\bibitem{Helios}
+E.A.~Vliiarino, R.J.J.~Stammler, A.A.~Ferri and J.J.~Casal, ``HELIOS: Angularly
+Dependent Collision Probabilities'', {\sl
+Nucl.~Sci.~Eng.}, {\bf 112}, 16-31 (1992).
+
+\bibitem{ecco}
+M. J.~Grimstone, J. D.~Tullett and G.~Rimpault, ``Accurate Treatments of
+Fast Reactor Fuel Assembly Heterogeneity with the ECCO Cell Code'',
+{\sl Proc. Int. Conf. on the Physics of Reactors: Operation, Design and
+Computation -- PHYSOR 90}, Marseille, France, p. IX:24, April 23-27 (1990).
+
+\bibitem{rimpault}
+G.~Rimpault, ``Algorithmic Features of the ECCO Cell Code for Treating
+Heterogeneous Fast Reactor Subassemblies", {\sl Int. Conf. on
+Mathematics and Computations, Reactor Physics, and Environmental Analyses},
+Portland, Oregon, April 30 -- May 4, 1995.
+
+\bibitem{PIJK0}
+P.~Benoist, J.~Mondot and I.~Petrovic, `Calculational and Experimental
+Investigations of Void Effect -- A Simple Theoretical Model for Space-Dependent
+Leakage Treatment of Heterogeneous Assemblies'', {\sl Nucl.~Sci.~Eng.}, {\bf
+118}, 197 (1994).
+
+\bibitem{PIJK}
+I.~Petrovic, P.~Benoist and G.~Marleau, ``A Quasi-Isotropic Reflecting Boundary
+Condition for the Heterogeneous Leakage Model Tibere'', {\sl Nucl.~Sci.~Eng.},
+{\bf 122}, 151 (1996)
+
+\bibitem{MATXS7A}
+``MATXS7A - 69 Neutron Group Cross Section Library in MATXS'', DLC-117, RSIC
+Data Library  Collection, Oak Ridge National Laboratory (1985).
+
+\bibitem{WIMKAL}
+J.-D. Kim, J.T. Lee, C.-S. Gil and H.R. Kim, ``Generation and Benchmarking of a 69--group Cross Section Library for Thermal Reactor Applications'', {\sl J. of the Korean Nucl. Soc.}, {\bf 21} 245 (1989).
+
+\bibitem{JEF}
+P.~Vontobel and S.~Pelloni, ``New JEF/EFF Based MATXS-Formatted Nuclear Data
+Libraries", {\sl Nucl.~Sci.~Eng.}, {\bf 101}, 298 (1989).
+
+\bibitem{ALSB1}
+A.~H\'ebert, ``A Consistent Technique for the Pin-by-Pin Homogenization of a
+Pressurized Water Reactor Assembly", {\sl Nucl.~Sci.~Eng.}, {\bf 113}, 227
+(1993).
+
+\bibitem{ALSB2}
+A.~H\'ebert and G.~Mathonni\`ere, ``Development of a Third-Generation {\sl
+Superhomog\'en\'eisation} Method for the Homogenization of a Pressurized Water
+Reactor Assembly", {\sl Nucl.~Sci.~Eng.}, {\bf 115}, 129 (1993).
+
+\bibitem{ALSB3}
+A.~H\'ebert , ``Development of a Second Generation SPH Technique for the
+Pin-by-Pin Homogenization of a Pressurized Water Reactor Assembly in Hexagonal
+Geometry'', {\sl Trans. Am. Nucl. Soc.}, {\bf 71}, 253 (1994).
+
+\bibitem{madrid2}
+P. Blanc-Tranchant, A. Santamarina, G. Willermoz and A. H\'ebert, ``Definition and Validation of a 2-D Transport
+Scheme for PWR Control Rod Clusters", 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{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{sphedf}
+T. Courau, M. Cometto, E. Girardi, D. Couyras and N. Schwartz, ``Elements of Validation of Pin-by-Pin Calculations with the Future EDF Calculation Scheme Based on APOLLO2 and COCAGNE Codes," Proceedings of ICAPP 08, Anaheim, CA USA, June 8--12, 2008.
+
+\bibitem{recipie}
+W.~H.~Press, B.~P.~Flannery, S.~A.~Teukolsky and W.~T.~Vetterling, ``Numerical
+Recipes, Second Edition (FORTRAN Version)'', Cambridge University Press,
+Cambridge (1994).
+
+\bibitem{MRG1}
+G.~Marleau, 
+``Fine Mesh 3--D Collision Probability Calculations Using the Lattice Code DRAGON'',
+\textsl{Int. Conf. on the Physics of Nuclear Science and Technology}, 
+Long Island, New York, October 5--8, 1998,
+
+\bibitem{MRG2}
+G.~Marleau, ``New Geometric Capabilities of DRAGON'',
+\textsl{Nineteenth Annual Conf. of the Canadian Nuclear Society}, 
+Toronto, Ontario, October 18--21, 1998,
+
+\bibitem{Kodeli2001a}
+I. Kodeli, ``Multidimensional Deterministic Nuclear Data Sensitivity and Uncertainty Code System: Method and Application,"
+{\sl Nucl.~Sci.~Eng.}, {\bf 138}, 45--66 (2001).
+
+\bibitem{Bidaud2009a}
+A. Bidaud, G. Marleau, and E. Nablat, ``Nuclear Data Uncertainty Analysis using the coupling of DRAGON with SUSD3D," M\&C 2009 , Saratoga Springs, NY (2009).
+
+\bibitem{nestle}
+P. J. Turinsky, R. M. K. Al-Chalabi, P. Engrand, H. N. Sarsour, F. X. Faure and  W. Guo, ``NESTLE: Few-group neutron diffusion equation solver utilzing the nodal expansion
+method for eigenvalue, adjoint, fixed-source steady-state and transient problem,'' Electric Power Research Center, North Carolina State University, Raleigh, NC 27695-7909 (1994).
+
+\bibitem{LLB}
+S. Marguet, {\sl The Physics of Nuclear Reactors}, Springer, 2018.
+
+\bibitem{Koebke}
+K. Koebke, H. Haase, L. Hetzelt, and H.-J. Winter, ``Application and Verification of the Simplified Equivalence Theory
+for Burnup States," {\sl Nucl. Sci. Eng.}, {\bf 92}, 56--65 (1986).
+
+\bibitem{Frohlicher}
+K. Fr\"{o}hlicher, V. Salino and A. H\'ebert, ``Investigating fission distribution behavior under various
+homogenization techniques for asymmetrical fuel assemblies and different reflector equivalence methods,"
+{\sl Ann. nucl. Energy}, {\bf 157}, 1--12 (2021).
+
+\bibitem{PSPLOT}
+K.E.~Kohler, 
+\textsl{PostScript for Technical Drawings PSPLOT: A FORTRAN-Callable PostScript Plotting
+Library User's Manual}, 
+Technical Report Nova Southeastern University, Oceanographic
+Center, 8000 North Ocean Drive, Dania, Florida; One can get a feel for the flavor of
+PSPLOT at \url{http://www.nova.edu/ocean/} while access to the full psplot library is via
+anonymous ftp: whitetip.ocean.nova.edu in the directory psplot. 
+
+\bibitem{GHOSTVIEW}
+T.O.~Theisen, 
+\textsl{Ghostview: An X11 user interface for Ghostscript}, 
+This program is free software under the term of the GNU general public licence as
+published by the Free Software Fundation.
+
+\bibitem{matlab}
+MATLAB, {\sl The Language of Technical Computing}, {\tt www.mathworks.com} (2006). 
+
+\bibitem{Plamondon2006}
+C. Plamondon, {\sl V\'erification des lignes d'int\'egration et illustration des g\'eom\'etries DRAGON}, Technical Report 
+IGE-290, \'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{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{Mostel}
+R.D.~Mosteller, L.D.~Eisenhart, R.C.~Little, W.J.~Eich and J.~Chao, ``Benchmark
+Calculations for the Doppler Coefficient of Reactivity", {\sl Nucl.~Sci.~Eng.},
+{\bf 107}, 265 (1991).
+
+\bibitem{Stankovski}
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-- 
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