Publications à Polytechnique

Ces données sont extraites du Répertoire des publications de l'École Polytechnique de Montréal. La liste ci-dessous contient seulement les publications auxquelles a participé le professeur ou le chercheur depuis son entrée en fonction à l’École. De plus, certaines publications ne sont pas dans cette liste, notamment les notes de cours et les rapports techniques internes plus d'information...
1	Kim, S.-M., Kim, H.-T., Donnelly, J.I.M., Marleau, G. (2012). Phase-B Pre-Simulation Using Boron and Gadolinium As Poison in the Moderator System for Wolsong-1. Nuclear Engineering and Technology, 44(5), p. 551-560.
2	Marleau, G., Chambon, R. (2011). Fukushima, des notions techniques aux enseignements pratiques en passant par les conséquences. La physique au Canada, 67(4), p. 267-271.
3	Laville, C., Marleau, G., Ivanova, T., Bernard, F., Richet, Y. (2011). Sensitivity Calculations for UACSA Beanchmark Phase III by IRSN. International Conference on Nuclear Criticality.
4	St-Aubin, E., Marleau, G. (2011). CANDU-6 Devices Reactivity Worth Adjustement for Advanced Fuel Cycles. 2nd International Conference on Physics and Technology of Reactors and Applications.
5	Bentoumi, G., Dai, X., Ho, A., Jonkmans, G., Li, L., Marleau, G. (2011). Simulation and Design of a Neutron Detector Based on Boron-Loaded Linear Alkyl Benzene (LAB) Liquid Scintillator. 32nd Annual Conference of the CNS.
6	Harrisson, G., Marleau, G. (2011). Modeling of a 3-D SCWR Unit Cell. 32nd Annual Conference of the CNS.
7	St-Aubin, E., Marleau, G. (2011). An Optimization Scheme for Selecting Alternative Fuels in CANDU-6 Reactor. 32nd Annual Conference of the CNS.
8	Martin, N., Hebert, A., Marleau, G. (2010). Dragon Solutions to the 3d Transport Benchmark Over a Range in Parameter Space. Annals of Nuclear Energy, 37(8), p. 1107-1114.
9	Marleau, G., Hebert, A. (2010). The GPT Saga at École Polytechnique. 31st CNS Annual Conference.
10	Lajoie, M.A., Marleau, G., Martin, N., Hebert, A. (2010). Application of 3D Collision Probability Method to VHTR Spherical Geometries. International Conference on Advances in Reactor Physics to Power the Nuclear Reanissance PHYSOR 2010.
11	Roy, R., Marleau, G., Hebert, A. (2010). Rudi Stamm'Ler Contributions and DRAGON. International Conference on Advances in Reactor Physics to Power the Nuclear Reanissance PHYSOR 2010.
12	Marleau, G., Kennedy, G., Chilian, C. (2010). Training New Operators for the SLOWPOKE Reactor at École Polytechnique : Theory and Practice. Technical Meeting on Low-Power Critical Facilities and Small Reactors.
13	Marleau, G., Veyret, P. (2010). Simulating Sample Irradiation in the SLOWPOKE Reactor Using the Lattice Code DRAGON. Technical Meeting on Low-Power Critical Facilities and Small Reactors.
14	Lajoie, M.A., Marleau, G. (2010). Application of the Full 3-D Collision Probability Method to Randomly Distributes Spherical Fuel Elements. 31st Annual Conference of the CNS.
15	Harrisson, G., Marleau, G. (2010). Models for Resonance Self-Shielding Calculation in Neutronic Analysis of the CANDU-SCWR Fuel Channel. 31st Annual Conference of the CNS.
16	Altiparmakow, D., Shen, W., Marleau, G., Rouben, B. (2010). Evolution of Computer Codes for CANDU Analysis. PHYSOR Topical Meeting.
17	Leroyer, H., Marleau, G. (2009). Dragon Evaluation of the Effect of Heterogeneous Environment on PWR Assemblies. International Conference on Mathematics, Computational Methods and Reactor Physics 2009, v. 2, p. 763-772.
18	Dion, M., Marleau, G. (2009). Comparison of Probabilistic and Deterministic Error Propagation Calculations in DRAGON. International Conference on Mathematics, Computational Methods and Reactor Physics 2009, v. 5, p. 2934-2945.
19	Bidaud, A., Marleau, G., Noblat, E. (2009). Nuclear Data Uncertainty Analysis Using the Coupling of DRAGON With SUSD3D. International Conference on Mathematics, Computational Methods and Reactor Physics 2009, v. 4, p. 2348-2357.
20	Popov, A.V., Fehri, M.F., Chambon, R.P., Marleau, G., Teyssedou, A., Olekhnovitch, A., Popescu, O.M., Mureithi, N.W. (2009). Ensuring Negative Coolant-Void Reactivity in CANDU Generation III+. International Conference on Mathematics, Computational Methods and Reactor Physics 2009, v. 4, p. 2306-2316.
21	Popov, A.V., Assawaroongruengchot, M., Marleau, G., Hebert, A., Karthikeyan, R. (2009). Validating Models for Coolant Void Reactivity Evaluation in CANDU Generation III+. International Conference on Mathematics, Computational Methods and Reactor Physics 2009, v. 4, p. 2703-2710.
22	Courau, T., Sjoden, G., Marleau, G. (2009). PWR Assembly Transport Calculation: A Validation Benchmark Using DRAGON, PENTRAN, and MCNP. International Conference on Mathematics, Computational Methods and Reactor Physics 2009, v. 1, p. 626-638.
23	Alcaro, F., Dulla, S., Marleau, G., Mund, E., Ravetto, P. (2009). Development of Dynamic Models for Neutron Transport Calculations. XXI International Conference on Transport Theroy.
24	Dahmani, M., Marleau, G., Le Tellier, R. (2008). Modeling Reactivity Devices for Advanced CANDU Reactors Using the Code DRAGON. Annals of Nuclear Energy, 35(5), p. 804-812.
25	Le Tellier, R., Marleau, G., Dahmani, M., Hebert, A. (2008). Improvements of the Reactivity Devices Modeling for the Advanced Candu Reactor. Annals of Nuclear Energy, 35(5), p. 868-876.
26	Assawaroongruengchot, M., Marleau, G. (2008). Coolant Void Reactivity Adjustments in Advanced Candu Lattices Using Adjoint Sensitivity Technique. Annals of Nuclear Energy, 35(3), p. 377-394.
27	Martin, N., Marleau, G., Hebert, A. (2008). A Premilinary Study of the OECD/NEA 3D Transport Problem Using the Lattice Code DRAGON. Symposium on Simulation Methods in Nuclear Engineering.
28	Le Tellier, R., Marleau, G., Hebert, A. (2008). Burn-Up Dependence of Coolant Void Reactivity for ACR-1000 Cell. International Conference on the Physics of Reactors.
29	Popov A. V., Chambon, R.P., Le Tellier, R., Marleau, G., Hebert, A. (2008). Models for Coolant Void Reactivity Evaluation in CANDU Generation II and III+. International Conference on the Physics of Reactors.
30	Popov, A.V., Marleau, G., Olkehnovitch, A. (2008). The Third Generation of Heavywater Moderated Reactors. 16th Pacific Basin Nuclear Conference.
31	Le Mer, J., Marleau, G. (2007). Dragon Evaluation of the Benchmark for the Doppler Reactivity Defect. Joint International Topical Meeting on Mathematics and Computations and Supercomputing in Nuclear Applications, M and C + SNA 2007, p. 12.
32	Assawaroongruengchot, M., Marleau, G. (2007). Perturbation Theory Based on the Method of Cyclic Characteristics. Nuclear Science and Engineering, 157(1), p. 30-50.
33	Assawaroongruengchot, M., Marleau, G. (2007). Multigroup Adjoint Transport Solution Using the Method of Cyclic Characteristics. Nuclear Science and Engineering, 155(1), p. 37-52.
34	Talebi, F., Marleau, G., Koclas, J. (2006). A Model for Coolant Void Reactivity Evaluation in Assemblies of Candu Cells. Annals of Nuclear Energy, 33(11-12), p. 975-983.
35	Varin, E., Marleau, G. (2006). CANDU Reactor Core Simulations Using Fully Coupled DRAGON and DONJON Calculations. Annals of Nuclear Energy, 33(8), p. 682-691.
36	Assawaroongruengchot, M., Marleau, G. (2006). Generalized Perturbation Theory Based on the Method of Cyclic Characteristics. PHYSOR-2006, v. 5, p. 2574-2583.
37	Nuttin, A., Guillemin, P., Courau, T., Marleau, G., Méplan, O., David, S., Michel-Sendis, F., Wilson, J.N. (2006). Study of CANDU Thorium-Based Fuel Cycles With Monte Carlo and Deterministric Methods. PHYSOR-2006.
38	Dahmani, M., Marleau, G., Varin, É. (2006). Effect of Burnup on ACR-700 3-D Reactivity Devices Cross Sections. PHYSOR-2006.
39	Le Tellier, R., Hébert, A., Marleau, G. (2006). The Implementation of a 3-D Characteristics Solver for the Generation of Incremental Cross Section for Reactivity Devices in a CANDU Reactor. PHYSOR-2006, v. 1, p. 558-567.
40	Varin, E., Marleau, G. (2005). Validating the History-Bases Method in DRAGON/DONJON Using G2 Core Follow-Up. CNS 2005 Annuel Conference.
41	Dufour, P., Marleau, G., Koclas, J. (2004). Computation of Surface Fluxes in the Lattice Code DRAGON. 25th Annual CNS Conference - Nuclear Energy: Meeting the Challenges.
42	Marleau, G. (2004). CANDU Adjuster Rods Incremental Cross Sections Evaluation: a Perturbative Approach. PHYSOR 2004 - The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments.
43	Varin, E., Marleau, G. (2004). First Attemp at a CANDU-6 Core Tracking Using the Coupled DRAGON/DONJON Calculations. 6th International Conference on Simulation Methods in Nuclear Engineering.
44	Courau, T., Marleau, G. (2003). Perturbation Theory for Lattice Cell Calculations. Nuclear Science and Engineering, 143(1), p. 19-32.
45	Dufour, P., Koclas, J., Marleau, G. (2003). Reactor Power Computation Using a Model With Three Pseudo-Fission Products. 24th Annual Canadian Nuclear Society Conference.
46	Marleau, G. (2003). Approximate Discontinuity Factor Evaluations in DRAGON. 24th Annual Canadian Nuclear Society Conference.
47	Marleau, G., Varin, É. (2003). Transport Analyses of 2-D CANDU Diffusion Calculations. American Nuclear Society Topical Meeting in Mathematics and Computations.
48	Varin, E., Marleau, G., Chambon, R. (2003). Transport-Diffusion Coupling for CANDU Reactor Core Follow-Up. International Conference on Supercomputing in Nuclear Applications SNA'2003.
49	Courau, T., Marleau, G. (2002). Adjoint and Generalized Adjoint Flux Calculations Using the Collision Probability Technique. Nuclear Science and Engineering, 141(1), p. 46-54.
50	Courau, T., Marleau, G. (2002). HELIOS Based Incremental Cross Sections Generated Using DRAGON. 60 p.
51	Marleau, G. (2002). Verification of DRAGON: Progress and Lessons Learned. 23rd Annual Canadian Nuclear Society Conference.
52	Marleau, G., Foissac, F. (2002). DRAGON Analysis of MOX Fueled VVER Cell Benchmarks. 23rd Annual Canadian Nuclear Society Conference.
53	Marleau, G., Hébert, A., Roy, R. (2002). DRAGON Programmer's Manual. (IGE-251 Revision 1). 500 p.
54	Marleau, G., Varin, E. (2002). Coolant Void Reactivity in a CANDU: a 2-D Transport/Diffusion Comparison. 22nd Canadian Nuclear Society Simulation Symposium.
55	Sarsour, H., Rahnema, F., Mosher, S., Turinsky, P., Serghiuta, D., Marleau, G., Courau, T. (2002). HELIOS//DRAGON//NESTLE Codes Simulation of Void Reactivity in a CANDU Core. 22nd Canadian Nuclear Society Simulation Symposium.
56	Sarsour, H., Turinsky, P., Rahnema, F., Mosher, S., Serghiuta, D., Marleau, G., Courau, T. (2002). Best Estimate HELIOS/DRAGON/NESTLE Codes Simulation of a LOCA Power Pulse for a Simplified CANDU-6 Core. 22nd Canadian Nuclear Society Simulation Symposium.
57	Sarsour, H., Turinsky, P., Rahnema, F., Mosher, S., Serghiuta, D., Marleau, G., Courau, T. (2002). HELIOS/DRAGON/NESTLE Codes Simulation of the Gentilly-3 Loss of Class 4 Power Event. 22nd Canadian Nuclear Society Simulation Symposium.
58	Courau, T., Marleau, G. (2001). Generalized Perturbation Theory in DRAGON: Application to CANDU Cell Calculations. 33nd Annual Conference of the Canadian Nuclear Society, p. 12.
59	Courau, T., Marleau, G. (2001). Generalized Perturbation Theory in DRAGON: Application to PWR Assembly Calculations. M&C 2001 American Nuclear Society International Meeting on Mathematical Methods for Nuclear Applications, p. 14.
60	Courau, T., Marleau, G. (2000). Calculating Adjoint Fluxes in the Code DRAGON Using the Collision Probability Method. PHYSOR 2000 Proceedings 2000 ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium, p. 822-833.
61	Roy, R., Marleau, G. (2000). DRAGON Solutions for Benchmark BWR Lattice Cell Problem. PHYSOR 2000 American Nuclear Society International Topical Meeting, Advances in Reactor Physics and Mathematics and Computation into the Next Millenium, p. 11.
62	Benjaafar, H., Marleau, G. (1999). Generation of Microscopic Pseudo Fission-Products Properties. Communicating the Nuclear Advantage. 39th Annual Canadian Nuclear Association Conference & 20th Annual Canadian Nuclear Society Conference, p. 123-133.
63	Boubcher, M., Marleau, G., Rozon, D. (1999). Development of an Isotopic Depletion Method for Reactor Core Calculations. Communicating the Nuclear Advantage. 39th Annual Canadian Nuclear Association Conference & 20th Annual Canadian Nuclear Society Conference, p. 72-83.
64	Marleau, G. (1999). Coherent Anistropic Scattering Homogenization in the B1 Leakage Model. M&C 1999 Mathematics and Computation, Reacto Physics and Environmental Analysis in Nucleaar Applications, p. 909-918.
65	Sissaoui, M.T., Marleau, G., Rozon, D. (1999). Candu Reactor Simulations Using the Feedback Model With Actinide Burnup History. Nuclear Technology, 125(2), p. 197-212.
66	Boubcher, M., Marleau, G., Rozon, D. (1998). Pseudo-Isotopes Generation for the 235U and 238U Depletion Chains. 19th Annual Conference of the Canadian Nuclear Society.
67	Marleau, G. (1998). Fine Mesh 3-D Collision Probability Calculations Using the Lattice Code DRAGON. Proc. Int. Conf. Phys. Nucl. Sci. Technol, v. 1, p. 523-530.
68	Marleau, G. (1998). New Geometric Capabilities of DRAGON. 19th Annual Conference of the Canadian Nuclear Society.
69	Marleau, G., Debos, E. (1998). Homogenization of Linearly Anisotropic Scattering Cross Sections in a Consistent B1 Heterogeneous Leakage Model. 19th Annual Conference of the Canadian Nuclear Society.
70	Marleau, G., Sissaoui, M.T., Rousseau, K. (1998). Simulation of Vanadium Detectors in DRAGON. 19th Annual Conference of the Canadian Nuclear Society, p. 7.1-7.11.
71	Shen, W., Rozon, D., Marleau, G. (1998). Parametric Analysis of Doppler Coefficient of Reactivity in DUPIC Fuel by DRAGON. 19th Annual Conference of the Canadian Nuclear Society, v. 19, p. 3C1.1-3C1.8.
72	Sissaoui, M.T., Marleau, G., Koclas, J. (1998). Xenon Transients Simulation Using the Reactor Code DONJON. 19th Annual Conference of the Canadian Nuclear Society, v. 19, p. 4C6.1-4C6.13.
73	Kennedy, G., Marleau, G. (1997). Refuelling the SLOWPOKE-2 Reactor at Ecole Polytechnique: Procedure and Proposed Experiments. Proceedings of the 1997 Canadian Nuclear Society Conference.
74	Koclas, J., Sissaoui, M.T., Marleau, G. (1997). Comparison Between the Multi-Group Improved and Generalized Quasistatic Methods for Different Numbers of Energy Groups. Annals of Nuclear Energy, 24(15), p. 1223-1232.
75	Marleau, G., Grammont, X. (1997). Fewgroup Burnup Calculations Using Time Dependent Microscopic Cross Sections. Proceedings of the 1997 Canadian Nuclear Society Conference.
76	Marleau, G., Noceir, S., Roy, R., Rozon, D. (1997). Dragon Modelling of the SLOWPOKE-2 Reactor at Ecole Polytechnique. Proceedings of the 1997 Canadian Nuclear Society Conference.
77	Sissaoui, M.T., Marleau, G., Rozon, D. (1997). Accounting for Actinide Burnup History in CANDU Reactor Simulations. Advances in Nuclear Fuel Management II : Proceedings of the Topical Meeting, v. 1, p. 9-21-9.
78	Marleau, G. (1996). A Validation of DRAGON Based on Lattice Experiments. Proc. - Int. Conf. Simul. Methods Nucl. Eng., 5th,, v. 2, p. P7-1-7.
79	Petrovic, I., Benoist, P., Marleau, G. (1996). Quasi-Isotropic Reflecting Boundary Condition for the TIBERE Heterogeneous Leakage Model. Nuclear Science and Engineering, 122(2), p. 151-166.
80	Roy, R., Hébert, A., Marleau, G. (1996). Comments on "Investigation of Interface-Current Solution Techniques for Coupled Heterogeneous Cells". Nuclear Science and Engineering, 122(2), p. 283-285.
81	Hébert, A., Marleau, G., Roy, R. (1995). Application of the Lattice Code DRAGON to CANDU Analysis. Transactions of the American Nuclear Society, 72, p. 335-337.
82	Marleau, G., Milgram, M.S. (1995). A DRAGON-MCNP Comparison of Axial Diffusion Subcoefficients. Transactions of the American Nuclear Society, 72, p. 163-164.
83	Marleau, G., Milgram, M.S. (1995). Dragon-MCNP Comparison of Void Reactivity Calculations. Proceedings of the 1995 16th Annual Conference of the Canadian Nuclear Society, p. 8.
84	Petrovic, I., Benoist, P., Marleau, G. (1995). A Simplified Heterogeneous B1 Model With Isotropically-Reflected Neutrons on Assembly Boundary. Proceedings International Conference on Mathematics and Computation, Reactor Physics, and Environmental Analyses, v. 1, p. 792-801.
85	Sissaoui, M.T., Marleau, G. (1995). Application of the Feedback Model for the History Base Using DRAGON. 19. CNS Simulation Symposium, p. 12.
86	Marleau, G. (1994). Response to "Comment on 'Analysis of Cluster Geometries Using the DP1 Approximation of the J+or- Technique". Nuclear Science and Engineering, 116(3), p. 225.
87	Marleau, G., Roy, R., Arsenault, B. (1994). Simulation of Reactivity Control Devices in a CANDU-6 Reactor Using DRAGON. 1994 Nuclear Simulation Symposium, p. 113-121.
88	Marleau, G., Roy, R., Hébert, A. (1994). Finite Element Solution to the Transport Equation. 15th Annual Conference of the Canadian Nuclear Society, v. 1, p. 3B-13.
89	Petrovic, I., Benoist, P., Marleau, G. (1994). A Simplified Heterogeneous B1 Model With Isotropically-Reflected Neutrons on Assembly Boundary. 1994 Nuclear Simulation Symposium, p. 45-54.
90	Qaddouri, A., Roy, R., Marleau, G., Goulard, B., Mayrand, M. (1994). Multigroup Flux Solvers on Parallel Architecture. 15th Annual Conference of the Canadian Nuclear Society.
91	Roy, R., Marleau, G., Tajmouati, J., Rozon, D. (1994). Modelling of CANDU Reactivity Control Devices With the Lattice Code DRAGON. Annals of Nuclear Energy, 21(2), p. 115-132.
92	Varin, E., Marleau, G., Roy, R. (1994). Towards the Generation of a Consistent Reactor Cross-Section Database for CANDU-6 Using DRAGON. 1994 Nuclear Simulation Symposium, p. 34-43.