diff options
Diffstat (limited to 'doc/IGE335/Bibliography.tex')
| -rw-r--r-- | doc/IGE335/Bibliography.tex | 570 |
1 files changed, 570 insertions, 0 deletions
diff --git a/doc/IGE335/Bibliography.tex b/doc/IGE335/Bibliography.tex new file mode 100644 index 0000000..3bc5fe9 --- /dev/null +++ b/doc/IGE335/Bibliography.tex @@ -0,0 +1,570 @@ +\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} +\v{Z}.~Stankovski, ``Refinement of the Substructure Method for Integral +Transport Calculations", {\sl Nucl.~Sci.~Eng.}, {\bf 92}, 255 (1986). + +\bibitem{Akroyd} +R.T.~Akroyd and N.S.~Riyait, ``Iteration and Extrapolation Methods for the +Approximate Solution of the Even-Parity Transport Equation for systems with +voids", {\sl Ann.~nucl.~Energy}, {\bf 16}, 1 (1989). + +\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{Kieffer} +C. Kieffer, ``Impl\'{e}mentation dans le code DRAGON d'un module de calcul de la masse volumique de l'eau l\'{e}g\`{e}re et lourde en fonction de la temp\'{e}rature et de la pression.," Technical Report IGE-315, \'Ecole Polytechnique de Montr\'eal (2009). + +\bibitem{Freesteam} +J. Pye, "Freesteam", (2013), + \url{http://freesteam.sourceforge.net/}. + +\bibitem{McMaster} +B. Garland, "Heavy Water Properties at McMaster University", (2015), \url{http://www.nuceng.ca/d2o/d2ohome.htm}. + +\bibitem{Marleau2001} +G. Marleau, ``DRAGON Theory Manual Part 1: Collision Probability Calculations," Technical Report IGE-236 +Rev. 1, \'Ecole Polytechnique de Montr\'eal (2001). + +\bibitem{sphedf2} +P. Gu\'erin, T. Courau, D. Couyras and E. Girardi, ``\'Equivalence et correction de transport dans COCAGNE," Compte-Rendu CR-I23/2010/042, SINETICS, \'Electricit\'e de France, January 2011. + +\bibitem{cns2015} +A.~H\'ebert, ``A Reformulation of the Transport-Transport SPH Equivalence Technique," paper presented at the +\textsl{7th International Conference on Modelling and Simulation in Nuclear Science and Engineering (7ICMSNSE)}, Ottawa, Canada, October 18--21, 2015. + +\bibitem{autosecol} +M. Grandotto-Biettoli, ``AUTOSECOL, un calcul automatique de l'auto-protection +des r\'esonances des isotopes lourds," Note CEA-N-1961, Commissariat \`a +l'\'Energie Atomique, 1977. + +\bibitem{vdg} +M. Coste, H. Tellier, P. Ribon, C. Raepsaet and C. Van Der Gucht, ``New improvements in the self-shielding +formalism of the APOLLO2 code," +{\sl Int. Top. Mtg. on mathematical methods and supercomputing in nuclear applications. M\&C$+$SNA}, +Karlsruhe, Germany, April 19 -- 23, 1993. + +\bibitem{salome} +A. Ribes and C. Caremoli, ``Salom\'e platform component model for numerical simulation,'' {\sl COMPSAC 07: Proceeding of the 31st Annual International Computer Software and Applications Conference}, pages 553-564, Washington, DC, USA, 2007, IEEE Computer Society. +See the website at \url{http://www.salome-platform.org}. + +\bibitem{tdt} +R. Sanchez, ``TDT, an advanced Integral Transport Method," {\sl Annual Meeting of the American Nuclear Society}, San-Diego, California, June 20-24, 1993. + +\bibitem{lyioussi} +N. Lyoussi-Charrat, ``Calcul du transport neutronique dans le code APOLLO2 par la m\'ethode des probabilit\'es de +collision dans une g\'eom\'etrie cart\'esienne g\'en\'erale," Th\`ese de doctorat, Universit\'e de Clermont-Ferrand 2, France, +Mars 1994. + +\bibitem{salt} +X. Warin, ``Notice th\'eorique de la m\'ethode des caract\'eristiques 2D et du g\'en\'erateur de trajectoires SALT," Report IGE-329, \'Ecole Polytechnique de Montr\'eal, Mars 2002. + +\bibitem{ane15b} +A. H\'ebert, ``DRAGON5 and DONJON5, the contribution of \'Ecole Polytechnique de Montr\'eal to the SALOME platform," {\sl Ann. nucl. Energy}, {\bf 87}, 12--20 (2016). + +\bibitem{alamos} +D. Tomatis, F. Bidault, A. Bruneton and Z. Stankovski, ``Overview of SERMA's Graphical User Interfaces for Lattice Transport Calculations,'' {\sl Energies}, vol. 15, no. 4, 2022. + +\bibitem{Harrisson2011a} + G.~Harrisson, and G.~Marleau, ``Modeling of a {3-D} {SCWR} unit cell,'' + {\sl 32nd Annual conference of the CNS}, Niagara Falls, ON (2011). + +\bibitem{Laville} +C. Laville, {\sl \'Etude de diff\'erentes m\'ethodes de calculs de coefficients de +sensibilit\'es du keff aux donn\'ees nucl\'eaires}, Master Thesis, \'Ecole Polytechnique de Montr\'eal (2011). + +\bibitem{SCALE} +``SCALE : A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation", +Oak Ridge National Laboratory, ORNL/TM-2005/39, Version 6.1 (2011). + +\bibitem{clio} +S. Perruchot-Triboulet and R. Sanchez, ``D\'ecomposition par m\'ethodes perturbatives de r\'eactivit\'e de deux syst\`emes,'' Note CEA-N-2817, Commissariat \`a l'\'Energie Atomique, France, F\'evrier 1997. + +\bibitem{todorova} +G. Todorova, H. Nishi and J. Ishibashi, ``Method for Condensation of the Macroscopic Transport Cross-Sections for Criticality Analyses of FBR MONJU by the Code NSHEX", {\sl J. of Nucl. Sci. and Tech.}, +{\bf 41}, No. 12, 1237 (2004). + +\bibitem{condPn} +J.-F. Vidal, P. Archier, B. Faure, V. Jouault, J.-M. Palau, V. Pascal, G. Rimpault, F. Auffret, L. Graziano, E. Masiello {\sl et al.}, ``Apollo3 +homogenization techniques for transport core calculations -- application to the Astrid CFV core," {\sl Nucl.~Eng.~and~Technology}, {\bf 49}, 1379 (2017). + +\bibitem{serpent} +J. Lepp\"anen, ``Serpent, a Continuous-energy Monte Carlo Reactor Physics Burnup Calculation Code,'' VTT Technical Research Centre, Finland, March 2013. + +\bibitem{edep} +R. Tuominen, V. Valtavirta and J. Lepp\"anen, ``New energy deposition treatment in the Serpent 2 Monte Carlo transport code,'' {\sl Ann.~nucl.~Energy}, {\bf 129}, 224 (2019). + +\bibitem{hdf5} +The HDF Group, \url{https://www.hdfgroup.org}. + +\bibitem{morel1996} +J.E. Morel, Leonard J. Lorence, Jr., Ronald P. Kensek, John A. Halbleib and D. P. Sloan, ``A Hybrid Multigroup/Continuous-Energy Monte Carlo Method for +Solving the Boltzmann-Fokker-Planck Equation,'' {\sl Nucl.~Eng.~and~Technology}, {\bf 124:3}, 369-389 (1996). + +\bibitem{cygwin} +The home of the Cygwin project, \url{http://www.cygwin.com/}. + +\bibitem{wsl} +Windows Subsystem for Linux, \url{https://learn.microsoft.com/en-us/windows/wsl/}. + +\bibitem{morel1989} +J. E. Morel, ``A Hybrid Collocation-Galerkin-$S_n$ Method for Solving the Boltzmann Transport Equation,'' {\sl Nucl.~Sci.~and~Eng.}, {\bf 101:1}, 72-87 (1989). + +\bibitem{shands2024} +E. W. Shands, J. T. Doe, M. R. Smith, and L. N. Brown, ``A New Galerkin Quadrature Method Not Requiring a Matrix Inverse,'' {\sl Nucl.~Sci.~and~Eng.}, {\bf 124}, 1-18 (2024). + +\end{thebibliography} |