Documents dont l'auteur est "Marleau, Guy"

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Guy MarleauGuy MarleauDépartement de génie physiqueVoir sa fiche dans le Répertoire des Expertises de Polytechnique Montréal
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Nombre de documents: 162

A

Adouki, P., & Marleau, G. (avril 2012). Neutronics/thermalhydraulics coupling in a CANDU SCWR [Communication écrite]. 3rd China-Canada Joint Workshop on Supercritical Water-Cooled Reactors (CCSC), Xi'an, Shaanxi, China. Non disponible

Altiparmakow, D., Shen, W., Marleau, G., & Rouben, B. (mai 2010). Evolution of computer codes for CANDU analysis [Communication écrite]. PHYSOR Topical Meeting, Pittsburgh, Pennsylvania. Lien externe

Alcaro, F., Dulla, S., Marleau, G., Mund, E., & Ravetto, P. (juillet 2009). Development of dynamic models for neutron transport calculations [Communication écrite]. XXI International Conference on Transport Theroy, Torino, Italy. Lien externe

Assawaroongruengchot, M., & Marleau, G. (2008). Coolant Void Reactivity Adjustments in Advanced CANDU Lattices Using Adjoint Sensitivity Technique. Annals of Nuclear Energy, 35(3), 377-394. Lien externe

Assawaroongruengchot, M., & Marleau, G. (2007). Multigroup adjoint transport solution using the method of cyclic characteristics. Nuclear Science and Engineering, 155(1), 37-52. Lien externe

Assawaroongruengchot, M., & Marleau, G. (2007). Perturbation Theory Based on the Method of Cyclic Characteristics. Nuclear Science and Engineering, 157(1), 30-50. Lien externe

Assawaroongruengchot, M., & Marleau, G. (septembre 2006). Generalized Perturbation Theory Based on the Method of Cyclic Characteristics [Communication écrite]. PHYSOR-2006, Vancouver, Canada. Non disponible

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Blinkhorn, M., Trancart, I., Preet, L., Marleau, G., & Situm, A. (2026). A Retrospective Analysis of the CANDU-3, Canada's Original Small Modular Reactor Design. Nuclear Technology, 15 pages. Lien externe

Billiet, G., Doligez, X., Marleau, G., Ernoult, M., Hébert, A., & Thiollière, N. (2024). Multi-physics DONJON5 reactor models for improved fuel cycle simulation with CLASS. EPJ Nuclear Sciences & Technologies, 13(5), 2024008 (13 pages). Disponible

Bejaoui, N., & Marleau, G. (avril 2014). Modelling of CANDU-SCWR unit cell with DRAGON: from Cartesian to hexagonal geometry [Communication écrite]. 2014 Canada-China Conference on Advanced Reactor Development (CCCARD-2014), Niagara Falls, Ontario Canada (10 pages). Lien externe

Bentoumi, G., Li, L., Jonkmans, G., Marleau, G., Sur, B., Fritzsche, H., & Dai, X. (2013). Characterization of a liquid scintillator based on linear alkyl benzene for neutron detection. Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 701, 221-224. Lien externe

Bejaoui, N., & Marleau, G. (octobre 2012). DRAGON simulation of a radial PWR reflector [Communication écrite]. 24th Nuclear Simulation Symposium, Ottawa, Ontario, Canada. Non disponible

Bentoumi, G., Dai, X., Ho, A., Jonkmans, G., Li, L., Marleau, G., & Sur, B. (juin 2011). Simulation and design of a neutron detector based on Boron-Loaded linear alkyl benzene (LAB) liquid scintillator [Communication écrite]. 32nd Annual Conference of the CNS, Niagara Falls, Canada (10 pages). Lien externe

Bidaud, A., Marleau, G., & Noblat, E. (mai 2009). Nuclear data uncertainty analysis using the coupling of DRAGON with SUSD3D [Communication écrite]. International Conference on Mathematics, Computational Methods and Reactor Physics 2009, Saratoga Springs, NY, United states. Non disponible

Boubcher, M., Marleau, G., & Rozon, D. (mai 1999). Development of an isotopic depletion method for reactor core calculations [Communication écrite]. Communicating the nuclear advantage. 39th Annual Canadian Nuclear Association Conference & 20th Annual Canadian Nuclear Society Conference, Montréal, QC, Canada. Lien externe

Benjaafar, H., & Marleau, G. (mai 1999). Generation of microscopic pseudo fission-products properties [Communication écrite]. Communicating the nuclear advantage. 39th Annual Canadian Nuclear Association Conference & 20th Annual Canadian Nuclear Society Conference, Montréal, Québec. Non disponible

Boubcher, M., Marleau, G., & Rozon, D. (octobre 1998). Pseudo-isotopes generation for the ²³⁵U and ²³⁸U depletion chains [Communication écrite]. 19th Annual Conference of the Canadian Nuclear Society, Toronto, Ontario (Canada). Lien externe

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Chambon, R., & Marleau, G. (avril 2012). Comparison of point kinetics, improved quasistatic and theta method as space-time kinetics solvers in donjon-3 simulations [Communication écrite]. International Conference on the Physics of Reactors 2012: Advances in Reactor Physics, PHYSOR 2012, Knoxville, TN, United states. Non disponible

Chambon, R., & Marleau, G. (avril 2012). DDGui, a new and fast way to analyse DRAGON and DONJON code results [Communication écrite]. International Conference on the Physics of Reactors 2012: Advances in Reactor Physics, PHYSOR 2012, Knoxville, TN, United states. Non disponible

Camand, C., & Marleau, G. (octobre 2012). Comparative study of DRAGON and TRIPOLI for a PWR assembly [Communication écrite]. 24th Nuclear Simulation Symposium, Ottawa, Ontario, Canada (11 pages). Lien externe

Courau, T., Sjoden, G., & Marleau, G. (mai 2009). PWR assembly transport calculation: A validation benchmark using DRAGON, PENTRAN, and MCNP [Communication écrite]. International Conference on Mathematics, Computational Methods and Reactor Physics 2009, Saratoga Springs, NY, United states. Non disponible

Courau, T., & Marleau, G. (2003). Perturbation theory for lattice cell calculations. Nuclear Science and Engineering, 143(1), 19-32. Lien externe

Courau, T., & Marleau, G. (2002). HELIOS based incremental cross sections generated using DRAGON. (Rapport technique). Non disponible

Courau, T., & Marleau, G. (2002). Adjoint and Generalized Adjoint Flux Calculations Using the Collision Probability Technique. Nuclear Science and Engineering, 141(1), 46-54. Lien externe

Courau, T., & Marleau, G. (janvier 2001). Generalized perturbation theory in DRAGON: application to PWR assembly calculations [Communication écrite]. M&C 2001 american nuclear society international meeting on mathematical methods for nuclear applications, Salt Lake City, UT, USA. Non disponible

Courau, T., & Marleau, G. (janvier 2001). Generalized perturbation theory in DRAGON: application to CANDU cell calculations [Communication écrite]. 33nd annual conference of the canadian nuclear society, Toronto, ON, Canada. Non disponible

Courau, T., & Marleau, G. (mai 2000). Calculating adjoint fluxes in the code DRAGON using the collision probability method [Communication écrite]. ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium (PHYSOR 2000), Pittsburgh, USA. Non disponible

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Dion, M., & Marleau, G. (2016). Sensitivity of cross sections to isotopic densities for subgroup resonance self-shielding calculations. Nuclear Science and Engineering, 183(2), 261-274. Lien externe

Dion, M., & Marleau, G. (2015). Eigenvalue implicit sensitivity to self-shielding calculations in heterogeneous geometries. Nuclear Science and Engineering, 179(2), 186-198. Lien externe

Dion, M., & Marleau, G. (septembre 2014). A collision probability based method to compute cross sections sensitivities for the subgroup self-shielding technique [Communication écrite]. ANS Reactor Physics Topical Meeting (PHYSOR), Kyoto, Japan. Non disponible

Dion, M., & Marleau, G. (mai 2013). Resonance self-shielding effects on eigenvalue sensitivity [Communication écrite]. International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2013, Sun Valley, ID, United states. Non disponible

Dion, M., & Marleau, G. (mai 2009). Comparison of probabilistic and deterministic error propagation calculations in DRAGON [Communication écrite]. International Conference on Mathematics, Computational Methods and Reactor Physics 2009, Saratoga Springs, NY, United states. Non disponible

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), 804-812. Lien externe

Duquette, J.-S., Marleau, G., & Chambon, R. (novembre 2008). Using Environment Dependent Cell Properties for ACR-1000 Core Calculations [Communication écrite]. 23rd CNS Nuclear Simulation Symposium, Ottawa, ON, Canada (15 pages). Lien externe

Dahmani, M., Marleau, G., & Varin, É. (septembre 2006). Effect of Burnup on ACR-700 3-D Reactivity Devices Cross Sections [Communication écrite]. PHYSOR-2006, Vancouver, Canada. Non disponible

Dufour, P., Marleau, G., & Koclas, J. (juin 2004). Computation of surface fluxes in the lattice code DRAGON [Communication écrite]. 25th annual CNS conference - Nuclear energy: meeting the challenges, Toronto, Ontario, Canada. Non disponible

Dufour, P., Koclas, J., & Marleau, G. (janvier 2003). Reactor power computation using a model with three pseudo-fission products [Communication écrite]. 24th annual canadian nuclear society conference, Toronto. Non disponible

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Faure, B., & Marleau, G. (2017). Simulation of a sodium fast core: Effect of B 1 leakage models on group constant generation. Annals of Nuclear Energy, 99, 484-494. Disponible

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Guasch, R., Huet, C., Hébert, A., Béguin, C., & Marleau, G. (avril 2025). Coupled Neutronics and Thermal Hydraulics Simulations of a BWR Fuel Channel in the Version5 Environment [Communication écrite]. International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025), Denver, CO, USA. Lien externe

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Housseiney Milany, S. R., & Marleau, G. (juin 2016). Implementation of a dominant modes solver in DRAGON [Communication écrite]. 36th Annual Conference of the Canadian Nuclear Society and 40th Annual CNS/CNA Student Conference, Toronto, ON. Lien externe

Housseiny Milany, S. R., & Marleau, G. (juin 2016). Application of the transport equation dominant modes in flux mapping [Communication écrite]. 36th Annual CNS Conference and 40th CNS-CNA Student Conference - Nuclear in the 21st Century: Global Directions and Canada's Role, Toronto, ON, Canada. Non disponible

Hébert, A., & Marleau, G. (mai 2016). DRAGON5 Workshop [Communication écrite]. Physics of Reactors (PHYSOR 2016): Unifying Theory and Experiments in the 21st Century, Sun Valley, Idaho. Non disponible

Hébert, A., & Marleau, G. (octobre 2015). Workshop 1 : Advancements in DRAGON : New Features of Version 5 [Communication écrite]. 7th International Conference on Modelling and Simulation in Nuclear Science and Engineering (ICMSNSE), Ottawa, Canada. Non disponible

Hébert, A., & Marleau, G. (octobre 2015). DRAGON5 Workshop [Communication écrite]. 7th International Conference on Modelling and Simulation in Nuclear Science and Engineering (7ICMSNSE), Ottawa, Canada. Non disponible

Harrisson, G., & Marleau, G. (2013). Simulation strategy for the evaluation of neutronic properties of a Canadian SCWR fuel channel. Science and Technology of Nuclear Installations, 2013, 1-10. Disponible

Harrisson, G., & Marleau, G. (avril 2012). 2-D and 3-D evaluation of neutronic properties along a caadian SCWR fuel channel [Communication écrite]. 3rd China-Canada Joint Workshop on Supercritical Water-Cooled Reactors (CCSC), Xi'an, Shaanxi, China. Non disponible

Harrisson, G., & Marleau, G. (avril 2012). Computation of a Canadian SCWR unit cell with deterministic and Monte Carlo codes [Communication écrite]. International Conference on the Physics of Reactors 2012: Advances in Reactor Physics, PHYSOR 2012, Knoxville, TN, United states. Non disponible

Harrisson, G., & Marleau, G. (juin 2011). Modeling of a 3-D SCWR unit cell [Communication écrite]. 32nd Annual Conference of the CNS, Niagara Falls, Canada (9 pages). Lien externe

Harrisson, G., & Marleau, G. (mai 2010). Models for resonance self-shielding calculation in neutronic analysis of the CANDU-SCWR fuel channel [Communication écrite]. 31st annual Conference of the CNS, Montréal, Québec (10 pages). Lien externe

Harrisson, G., & Marleau, G. (avril 2010). Models for Safety Analysis of the Generation IV Supercritical Water-cooled Reactor [Communication écrite]. 2nd Canada-China Joint Workshop on Supercritical Water-Cooled Reactors (CCSC 2010), Toronto, ON, Canada (11 pages). Lien externe

Hébert, A., Marleau, G., & Roy, R. (juin 1995). Application of the lattice code DRAGON to CANDU analysis [Communication écrite]. Annual meeting of the American Nuclear Society (ANS), Philadelphia, Penn.. Publié dans Transactions of the American Nuclear Society, 72. Non disponible

Hébert, A., Marleau, G., & Roy, R. (juin 1995). Application of the lattice code DRAGON to CANDU reactor analysis [Communication écrite]. Annual Meeting and the Embedded Topical Meeting on Computer-Based Human Support Systems of American Nuclear Society (ANS 1995), Philadelphia, PA. Non disponible

Hébert, A., & Marleau, G. (1991). Generalization of the Stamm'ler Method for the Self-Shielding of Resonant Isotopes in Arbitrary Geometries. Nuclear Science and Engineering, 108(3), 230-239. Lien externe

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Inzirillo, F., Brighenti, A., Cammi, A., Graziano, L., Hébert, A., Marleau, G., Santandrea, S., & Vezzoni, B. (avril 2024). Towards 2D reference deterministic calculations in support of industrial model verification and advanced reflector modeling setup [Communication écrite]. 2024 International Conference on Physics of Reactors (PHYSOR 2024), San Francisco, CA, USA. Lien externe

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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), 551-560. Lien externe

Karthikeyan, R., Hébert, A., & Marleau, G. (septembre 2005). Effects of advanced self shielding and burnup models on fuel temperature coefficient estimation for a Candu-6 assembly [Communication écrite]. International Topical Meeting on Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications (M&C 2005), Avignon, France. Non disponible

Karthikeyan, R., Hébert, A., & Marleau, G. (juin 2005). Depleting a CANDU-6 fuel assembly using detailed burnup data and reactionwise energy release [Communication écrite]. 26th Annual CNS Conference (CSN 2005), Toronto, ON. Non disponible

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), 1223-1232. Lien externe

Kennedy, G. G., & Marleau, G. (juin 1997). Refuelling the SLOWPOKE-2 reactor at École Polytechnique: Procedure and proposed experiments [Communication écrite]. 1997 Canadian Nuclear Society Conference, Toronto, Can. Lien externe

Koclas, J., Roy, R., & Marleau, G. (juin 1993). Drift Effects in CANDU Reactors [Communication écrite]. 4th International Conference on Simulation Methods in Nuclear Engineering, Montréal, Québec (12 pages). Lien externe

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Le Tennier, U., & Marleau, G. (2024). Neutronics-thermalhydraulics coupled analysis of Canadian SCWR based on DONJON5 and CATHENA. Nuclear Engineering and Design, 426, 113346 (11 pages). Lien externe

Liegeard, C., Calloo, A., Marleau, G., & Girardi, E. (avril 2017). Impact of photon transport on power distribution [Communication écrite]. International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering (M&C 2017), Jeju, Korea (8 pages). Lien externe

Lajoie, M.-A., Févotte, F., & Marleau, G. (octobre 2013). A generalization of 3D prismatic characteristics along a nonuniform projection mesh [Communication écrite]. Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2013, SNA & MC 2013, Paris, France (8 pages). Lien externe

Laville, C., Marleau, G., Ivanova, T., Bernard, F., & Richet, Y. (septembre 2011). Sensitivity calculations for UACSA benchmark phase III by IRSN [Communication écrite]. International Conference on Nuclear Criticality, Edinburgh, UK. Non disponible

Lajoie, M. A., Marleau, G., Martin, N., & Hébert, A. (mai 2010). Application of 3D collision probability method to VHTR spherical geometries [Communication écrite]. International Conference on Advances in Reactor Physics to Power the Nuclear Renaissance (PHYSOR 2010), Pittsburgh, Pennsylvania. Non disponible

Lajoie, M. A., & Marleau, G. (mai 2010). Application of the full 3-D collision probability method to randomly distributes spherical fuel elements [Communication écrite]. 31st annual Conference of the CNS, Montréal, Québec. Non disponible

Leroyer, H., & Marleau, G. (mai 2009). Dragon evaluation of the effect of heterogeneous environment on PWR assemblies [Communication écrite]. International Conference on Mathematics, Computational Methods and Reactor Physics 2009, Saratoga Springs, NY, United states. Non disponible

Le Tellier, R., Marleau, G., & Hébert, A. (septembre 2023). Burn-up dependence of coolant void reactivity for ACR-1000 cell [Communication écrite]. International Conference on the Physics of Reactors, Interlaken, Switzerland. Non disponible

Le Tellier, R., Marleau, G., Dahmani, M., & Hébert, A. (2008). Improvements of the Reactivity Devices Modeling for the Advanced CANDU Reactor. Annals of Nuclear Energy, 35(5), 868-876. Lien externe

Le Mer, J., & Marleau, G. (avril 2007). Dragon evaluation of the benchmark for the Doppler reactivity defect [Communication écrite]. Joint International Topical Meeting on Mathematics and Computations and Supercomputing in Nuclear Applications, M and C + SNA 2007, Monterey, CA, United States. Lien externe

Le Tellier, R., Hébert, A., & Marleau, G. (septembre 2006). The Implementation of a 3-D Characteristics Solver for the Generation of Incremental Cross Section for Reactivity Devices in a CANDU Reactor [Communication écrite]. Advances in Nuclear Analysis and Simulation (PHYSOR 2006), Vancouver, Canada. Non disponible

Le Roy, R. J., Hébert, A., & Marleau, G. (1993). Consistent Bₙ Theory for Slab Lattices. Nuclear Science and Engineering, 115(2), 112-128. Lien externe

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Musongela, M., & Marleau, G. (2022). Generalization of the tibere B1 leakage model to the method of characteristics. Annals of Nuclear Energy, 174, 9 pages. Lien externe

Marleau, G., & Hébert, A. (octobre 2018). DRAGON5 Workshop [Communication écrite]. 8th International Conference on Simulation Methods in Nuclear Science and Engineering (8ICSMNSE), Ottawa, ON. Non disponible

Milany, S. R. H., & Marleau, G. (avril 2017). A hybrid stochastic deterministic approach for full core neutronics [Communication écrite]. International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering (M&C 2017), Jeju, Korea (8 pages). Lien externe

Marleau, G., & Chambon, R. (2011). Fukushima, des notions techniques aux enseignements pratiques en passant par les conséquences. Physique au Canada, 67(4), 267-271. Lien externe

Martin, N., Hébert, A., & Marleau, G. (2010). DRAGON Solutions to the 3D Transport Benchmark Over a Range in Parameter Space. Annals of Nuclear Energy, 37(8), 1107-1114. Lien externe

Marleau, G., & Veyret, P. (novembre 2010). Simulating sample irradiation in the SLOWPOKE reactor using the lattice code DRAGON [Communication écrite]. Technical Meeting on Low-Power Critical Facilities and Small Reactors, Ottawa, Canada. Non disponible

Marleau, G., Kennedy, G. G., & Chilian, C. (novembre 2010). Training new operators for the SLOWPOKE reactor at École Polytechnique : Theory and practice [Communication écrite]. Technical Meeting on Low-Power Critical Facilities and Small Reactors, Ottawa, Canada. Non disponible

Marleau, G., & Hébert, A. (mai 2010). The GPT Saga at École Polytechnique [Communication écrite]. 31st CNS Annual Conference, Montréal, Québec. Lien externe

Martin, N., Marleau, G., & Hébert, A. (novembre 2023). A preliminary study of the OECD/NEA 3D transport problem using the lattice code DRAGON [Communication écrite]. Symposium on Simulation Methods in Nuclear Engineering, Ottawa, Canada (14 pages). Lien externe

Marleau, G. (avril 2004). CANDU adjuster rods incremental cross sections evaluation: a perturbative approach [Communication écrite]. PHYSOR 2004 - The physics of fuel cycles and advanced nuclear systems: global developments, Chicago, illinois, USA. Non disponible

Marleau, G., & Varin, É. (janvier 2003). Transport analyses of 2-D CANDU diffusion calculations [Communication écrite]. American nuclear society topical meeting in mathematics and computations, Gatlinburg, Tennessee, USA. Non disponible

Marleau, G. (janvier 2003). Approximate discontinuity factor evaluations in DRAGON [Communication écrite]. 24th annual canadian nuclear society conference, Toronto. Non disponible

Marleau, G., & Varin, É. (janvier 2002). Coolant void reactivity in a CANDU: a 2-D transport/diffusion comparison [Communication écrite]. 22nd canadian nuclear society simulation symposium, Ottawa (15 pages). Lien externe

Marleau, G., Hébert, A., & Roy, R. (2002). DRAGON programmer's manual. (Rapport technique). Non disponible

Marleau, G., & Foissac, F. (janvier 2002). DRAGON analysis of MOX fueled VVER cell benchmarks [Communication écrite]. 23rd annual canadian nuclear society conference, Toronto. Non disponible

Marleau, G. (janvier 2002). Verification of DRAGON: progress and lessons learned [Communication écrite]. 23rd annual canadian nuclear society conference, Toronto. Non disponible

Marleau, G. (septembre 1999). Coherent anisotropic scattering homogenization in the B1 leakage model [Communication écrite]. M&C 1999 mathematics and computation, reactor physics and environmental analysis in nuclear applications, Madrid, Spain. Non disponible

Marleau, G., Sissaoui, M. T., & Rousseau, K. (1998). Simulation of Vanadium detectors in DRAGON [Communication écrite]. 19th Annual Conference of the Canadian Nuclear Society. Lien externe

Marleau, G., & Debos, E. (octobre 1998). Homogenization of linearly anisotropic scattering cross sections in a consistent B₁ heterogeneous leakage model [Communication écrite]. 19th Annual Conference of the Canadian Nuclear Society, Toronto, Ontario (Canada) (9 pages). Lien externe

Marleau, G. (octobre 1998). New geometric capabilities of DRAGON [Communication écrite]. 19th Annual Conference of the Canadian Nuclear Society, Toronto, Ontario (Canada) (17 pages). Lien externe

Marleau, G. (octobre 1996). Fine mesh 3-D collision probability calculations using the lattice code DRAGON [Communication écrite]. International Conference on the Physics of Nuclear Science and Technology, Long Island, NY. Non disponible

Marleau, G., Noceir, S., Roy, R., & Rozon, D. (juin 1997). Dragon modelling of the SLOWPOKE-2 reactor at École Polytechnique [Communication écrite]. 1997 Canadian Nuclear Society Conference, Toronto, Can. Lien externe

Marleau, G., & Grammont, X. (juin 1997). Fewgroup burnup calculations using time dependent microscopic cross sections [Communication écrite]. 1997 Canadian Nuclear Society Conference, Toronto, Can. Non disponible

Marleau, G. A validation of DRAGON based on lattice experiments [Communication écrite]. 5th International Conference on Simulation Methods in Nuclear Engineering, Montréal, Québec. Non disponible

Marleau, G., & Milgram, M. S. (juin 1995). A DRAGON-MCNP comparison of axial diffusion subcoefficients [Communication écrite]. 1995 Annual Meeting of American Nuclear Society, Philadelphia, PA. Publié dans Transactions of the American Nuclear Society, 72. Non disponible

Marleau, G., & Milgram, M. S. (juin 1995). Dragon-MCNP comparison of void reactivity calculations [Communication écrite]. 1995 16th Annual Conference of the Canadian Nuclear Society, Saskatoon, Can. Non disponible

Marleau, G., Roy, R., & Hébert, A. (juin 1994). Finite element solution to the transport equation [Communication écrite]. 15th Annual Conference of the Canadian Nuclear Society (CSN 1994), Montréal, Québec. Non disponible

Marleau, G., Roy, R., & Arsenault, B. (octobre 1994). Simulation of reactivity control devices in a CANDU-6 reactor using DRAGON [Communication écrite]. 1994 nuclear simulation symposium, Pembroke (Canada). Non disponible

Marleau, G. (1994). Response to "Comment on 'Analysis of cluster geometries using the DP1 approximation of the J₊ₒᵣ₋ technique" [Commentaire ou lettre]. Nuclear Science and Engineering, 116(3), 225-225. Lien externe

Marleau, G., & Roy, R. (juin 1993). Use of Specular Boundary Conditions for CANDU Cell Analysis [Communication écrite]. 4th International Conference on Simulation Methods in Nuclear Engineering, Montréal, Québec (14 pages). Lien externe

Marleau, G., & Hébert, A. (1992). Analysis of Cluster Geometries Using the DP1 Approximation of the J± Technique. Nuclear Science and Engineering, 111(3), 257-270. Lien externe

Marleau, G., Roy, R., Tajmouati, J., & Rozon, D. (1992). Burnup of Gentilly-2 Cell with DRAGON [Communication écrite]. Annual Reactor Simulation Symposium (21 pages). Lien externe

Marleau, G., Le Roy, R. J., & Hébert, A. (1990). Analytic Reductions for Transmission and Leakage Probabilities in Finite Tubes and Hexahedra. Nuclear Science and Engineering, 104(3), 209-216. Lien externe

Marleau, G., Roy, R., Hébert, A., & Paradis, E. (avril 1990). Comparison of Monte Carlo and Interface Current Solutions to 3D Transport Problems [Communication écrite]. 3rd International Conference on Simulation Methods in Nuclear Engineering, Montréal, Québec. Lien externe

Marleau, G., & Hébert, A. (1988). A Universal Driver for Collision Probability and Response Matrix Transport Codes [Communication écrite]. 1988 Annual Reactor Simulation Symposium (16 pages). Lien externe

Marleau, G., & Hébert, A. (1986). Interface Current Method for Cluster Geometry. Nuclear Science and Engineering, 92(2), 240-246. Lien externe

Marleau, G., Hébert, A., & Roy, R. (octobre 1986). Acceleration Strategies for the Interface Current Method [Communication écrite]. 2nd International Conference on Simulation Methods in Nuclear Engineering, Montréal, Québec. Lien externe

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Naceur, A., & Marleau, G. (2019). CANDU-6 operation simulations using accident tolerant cladding candidates. Annals of Nuclear Energy, 124, 472-489. Disponible

Naceur, A., & Marleau, G. (2017). Neutronic analysis for accident tolerant cladding candidates in CANDU-6 reactors. Annals of Nuclear Energy, 113, 147-161. Disponible

Nuttin, A., Guillemin, P., Courau, T., Marleau, G., Méplan, O., David, S., Michel-Sendis, F., & Wilson, J. N. (septembre 2006). Study of CANDU Thorium-based Fuel Cycles with Monte Carlo and Deterministic Methods [Communication écrite]. PHYSOR-2006, Vancouver, Canada. Non disponible

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Paradis, M., Doligez, X., Marleau, G., Ernoult, M., & Thiollière, N. (juin 2021). DONJON5/CLASS coupled simulations of MOX/UO2 heterogeneous PWR core [Communication écrite]. 2021 Technical Workshop on Nuclear Fuel Cycle Simulation (TWoFCS 2021) (14 pages). Publié dans EPJ Nuclear Sciences & Technologies, 8. Lien externe

Prabha, H., Karthikeyan, R., Lajoie, M.-A., Marleau, G., & Hébert, A. (2017). Multiplication factors of single pin hexagonal cells and VVER-1000 reactor assembly. Annals of Nuclear Energy, 109, 720-725. Lien externe

Prabha, H., Marleau, G., & Hébert, A. (2014). Tracking algorithms for multi-hexagonal assemblies (2D and 3D). Annals of Nuclear Energy, 69, 175-182. Lien externe

Prabha, H., & Marleau, G. (2013). Computation of 3D neutron fluxes in one pin hexagonal cell. Annals of Nuclear Energy, 56, 1-6. Lien externe

Prabha, H., & Marleau, G. (avril 2012). Computation of neutron fluxes in clusters of fuel pins arranged in hexagonal assemblies (2D and 3D) [Communication écrite]. International Conference on the Physics of Reactors 2012: Advances in Reactor Physics, PHYSOR 2012, Knoxville, TN, United states. Non disponible

Popov, A. V., Fehri, M. F., Chambon, R. P., Marleau, G., Teyssedou, A., Olekhnovitch, A., Popescu, O. M., & Mureithi, N. W. (mai 2009). Ensuring negative coolant-void reactivity in CANDU Generation III+ [Communication écrite]. International Conference on Mathematics, Computational Methods and Reactor Physics, Saratoga Springs, NY, United states. Non disponible

Popov, A. V., Assawaroongruengchot, M., Marleau, G., Hébert, A., & Karthikeyan, R. (mai 2009). Validating models for coolant void reactivity evaluation in CANDU Generation III+ [Communication écrite]. International Conference on Mathematics, Computational Methods and Reactor Physics 2009, Saratoga Springs, NY, United states. Non disponible

Popov, A. V., Chambon, R. P., Le Tellier, R., Marleau, G., & Hébert, A. (septembre 2023). Models for coolant void reactivity evaluation in CANDU Generation II and III+ [Communication écrite]. International Conference on the Physics of Reactors, Interlaken, Switzerland. Non disponible

Popov, A. V., Marleau, G., & Olekhnovitch, A. (octobre 2008). The third generation of heavywater moderated reactors [Communication écrite]. 16th Pacific Basin Nuclear Conference, Aomori, Japan. Non disponible

Petrović, I., Benoist, P., & Marleau, G. (1996). Quasi-isotropic reflecting boundary condition for the TIBERE heterogeneous leakage model. Nuclear Science and Engineering, 122(2), 151-166. Lien externe

Petrovic, I., Benoist, P., & Marleau, G. (avril 1995). A simplified heterogeneous B₁ model with isotropically-reflected neutrons on assembly boundary [Communication écrite]. International Conference on Mathematics and Computation, Reactor Physics, and Environmental Analyses, Portland, OR, USA. Non disponible

Petrovic, I., Benoist, P., & Marleau, G. (octobre 1994). A simplified heterogeneous B1 model with isotropically-reflected neutrons on assembly boundary [Communication écrite]. 1994 nuclear simulation symposium, Pembroke (Canada). Non disponible

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Qaddouri, A., Roy, R., Marleau, G., Goulard, B., & Mayrand, M. (juin 1994). Multigroup flux solvers on parallel architecture [Communication écrite]. 15th Annual Conference of the Canadian Nuclear Society, Montréal, Québec. Non disponible

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Raouafi, H., & Marleau, G. (2016). Monte Carlo simulation of inclined reactivity control rod and boron poisoning for the Canadian-SCWR Supercell. Journal of Nuclear Engineering and Radiation Science, 2(2), 7 pages. Lien externe

Raouafi, H., & Marleau, G. (août 2014). A simplified 3D DRAGON simulation of an inclined reactivity control device for the Canadian-SCWR [Communication écrite]. 19th Pacific Basin Nuclear Conference (PBNC 2014), Vancouver, British Columbia, Canada. Non disponible

Raouafi, H., & Marleau, G. (octobre 2012). DRAGON and SERPENT 2-D modelling of the SLOWPOKE-2 reactor at École Polytechnique Montréal [Communication écrite]. 24th Nuclear Simulation Symposium, Ottawa, Ontario, Canada (9 pages). Lien externe

Raouafi, H., & Marleau, G. (octobre 2012). DRAGON 2-D simulation of spatial self-shielding effect in SLOWPOKE-2 reactor [Communication écrite]. 24th Nuclear Simulation Symposium, Ottawa, Ontario, Canada. Non disponible

Roy, R., Marleau, G., & Hébert, A. (mai 2010). Rudi Stamm'ler contributions and DRAGON [Communication écrite]. International Conference on Advances in Reactor Physics to Power the Nuclear Renaissance (PHYSOR 2010), Pittsburgh, Pennsylvania. Non disponible

Roy, R., & Marleau, G. (mai 2000). DRAGON solutions for benchmark BWR lattice cell problem [Communication écrite]. PHYSOR 2000 american nuclear society international topical meeting, advances in reactor physics and mathematics and computation into the next millennium, Pittsburgh, PA, USA. Lien externe

Roy, R., & Marleau, G. (mai 2020). Dragon solutions for benchmark BWR lattice cell problems [Communication écrite]. ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium (PHYSOR 2000), Pittsburgh, PA, USA. Non disponible

Roy, R., Hébert, A., & Marleau, G. (1996). Comments on "Investigation of Interface-Current Solution Techniques for Coupled Heterogeneous Cells" [Commentaire ou lettre]. Nuclear Science and Engineering, 122(2), 283-285. Lien externe

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), 115-132. Lien externe

Roy, R., Marleau, G., Tajmouati, J., & Rozon, D. (juin 1993). Modelling of CANDU Reactivity Mechanisms with DRAGON [Communication écrite]. 4th International Conference on Simulation Methods in Nuclear Engineering, Montréal, Québec (16 pages). Lien externe

Roy, R., Hébert, A., & Marleau, G. (1989). A Transport Method for Treating Three-Dimensional Lattices of Heterogeneous Cells. Nuclear Science and Engineering, 101(3), 217-225. Lien externe

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St-Aubin, E., & Marleau, G. (2018). CANDU-6 reactivity devices optimization for advanced cycles – Part II: Liquid zone controllers adjustment. Nuclear Engineering and Design, 337, 460-470. Disponible

St-Aubin, E., & Marleau, G. (2018). CANDU-6 reactivity devices optimization for advanced fuel cycles - Part I: Adjuster rods optimization. Nuclear Engineering and Design, 337, 471-481. Lien externe

St-Aubin, E., & Marleau, G. (2015). CANDU-6 fuel optimization for advanced cycles. Nuclear Engineering and Design, 293, 371-384. Disponible

St-Aubin, E., & Marleau, G. (2015). Optimized CANDU-6 cell and reactivity device supercell models for advanced fuels reactor database generation. Annals of Nuclear Energy, 85, 331-336. Lien externe

St-Aubin, E., & Marleau, G. (avril 2012). Modeling CANDU-6 liquid zone controllers for effects of thorium-based fuels [Communication écrite]. International Conference on the Physics of Reactors 2012: Advances in Reactor Physics, PHYSOR 2012, Knoxville, TN, United states. Non disponible

St-Aubin, E., & Marleau, G. (juin 2011). An optimization scheme for selecting alternative fuels in CANDU-6 reactor [Communication écrite]. 32nd Annual Conference of the CNS, Niagara Falls, Canada (13 pages). Lien externe

St-Aubin, E., & Marleau, G. (septembre 2011). CANDU-6 devices reactivity worth adjustment for advanced fuel cycles [Communication écrite]. 2nd International Conference on Physics and Technology of Reactors and Applications, Fez, Morocco. Non disponible

Sarsour, H., Turinsky, P., Rahnema, F., Mosher, S., Serghiuta, D., Marleau, G., & Courau, T. (janvier 2002). Best estimate HELIOS/DRAGON/NESTLE codes simulation of a LOCA power pulse for a simplified CANDU-6 core [Communication écrite]. 22nd canadian nuclear society simulation symposium, Ottawa. Non disponible

Sarsour, H., Turinsky, P., Rahnema, F., Mosher, S., Serghiuta, D., Marleau, G., & Courau, T. (janvier 2002). HELIOS/DRAGON/NESTLE codes Simulation of the Gentilly-3 loss of class 4 power event [Communication écrite]. 22nd canadian nuclear society simulation symposium, Ottawa. Non disponible

Sarsour, H., Rahnema, F., Mosher, S., Turinsky, P., Serghiuta, D., Marleau, G., & Courau, T. (janvier 2002). HELIOS//DRAGON//NESTLE codes simulation of void reactivity in a CANDU core [Communication écrite]. 22nd canadian nuclear society simulation symposium, Ottawa. Non disponible

Sarsour, H. N., Rahnema, F., Mosher, S., Turinsky, P. J., Serghiuta, D., Marleau, G., & Courau, T. (novembre 2002). HELIOS/DRAGON/NESTLE Codes' Simulation of the Gentilly-2 Loss of Class 4 Power Event [Communication écrite]. 22nd Canadian Nuclear Society Nuclear Simulation Symposium, Ottawa, Ontario, Canada (12 pages). Lien externe

Sarsour, H. N., Rahnema, F., Mosher, S., Turinsky, P. J., Serghiuta, D., Marleau, G., & Courau, T. (novembre 2002). Best Estimate HELIOS/DRAGON/NESTLE Codes' Simulation of a LOCA Power Pulse for a Simplified CANDU-6 Core [Communication écrite]. 22nd Canadian Nuclear Society Nuclear Simulation Symposium, Ottawa, Ontario, Canada (11 pages). Lien externe

Sissaoui, M. T., Marleau, G., & Rozon, D. (1999). CANDU Reactor Simulations Using the Feedback Model With Actinide Burnup History. Nuclear Technology, 125(2), 197-212. Lien externe

Sissaoui, M. T., Marleau, G., & Koclas, J. (octobre 1998). Xenon transients simulation using the reactor code DONJON [Communication écrite]. 19th Annual Conference of the Canadian Nuclear Society, Toronto, Ontario (Canada). Lien externe

Shen, W., Rozon, D., & Marleau, G. Parametric analysis of Doppler coefficient of reactivity in DUPIC fuel by DRAGON [Communication écrite]. 19th Annual Conference of the Canadian Nuclear Society. Lien externe

Sissaoui, M. T., Marleau, G., & Rozon, D. Accounting for actinide burnup history in CANDU reactor simulations [Communication écrite]. Advances in nuclear fuel management II : topical meeting. Non disponible

Sissaoui, M. T., & Marleau, G. (octobre 1995). Application of the feedback model for the history base using DRAGON [Communication écrite]. 19. CNS simulation symposium, Hamilton (Canada). Non disponible

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Trancart, I., Marleau, G., & Doligez, X. (octobre 2024). Full core SSR-W simulations using DONJON5 [Communication écrite]. 5th Genration IV and Small Reactors Conference (G4SR 2024), Ottawa, ON, Canada (13 pages). Lien externe

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), 975-983. Lien externe

Tajmouati, J., Rozon, D., Marleau, G., & Roy, R. (1992). Comparison of Time-Average Power Distributions in a CANDU-600 Based on PPV, WIMS and DRAGON Lattice Properties [Communication écrite]. Annual Reactor Simulation Symposium (41 pages). Lien externe

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Varin, E., & Marleau, G. (2006). CANDU reactor core simulations using fully coupled DRAGON and DONJON calculations. Annals of Nuclear Energy, 33(8), 682-691. Lien externe

Varin, É., & Marleau, G. (juin 2023). Validating the history-bases method in DRAGON/DONJON using G2 core follow-up [Communication écrite]. CNS 2005 Annuel Conference, Toronto. Non disponible

Varin, É., & Marleau, G. (janvier 2004). First attempt at a CANDU-6 core tracking using the coupled DRAGON/DONJON calculations [Communication écrite]. 6th international conference on simulation methods in nuclear engineering, Montréal, Québec. Non disponible

Varin, É., Marleau, G., & Chambon, R. (janvier 2003). Transport-diffusion coupling for CANDU reactor core follow-up [Communication écrite]. International conference on supercomputing in nuclear applications SNA'2003, Paris, France. Lien externe

Varin, É., Marleau, G., & Roy, R. (octobre 1994). Towards the generation of a consistent reactor cross-section database for CANDU-6 using DRAGON [Communication écrite]. 1994 nuclear simulation symposium, Pembroke (Canada). Non disponible

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Zadeh, F. M., Étienne, S., Chambon, R., Marleau, G., & Teyssedou, A. (2016). Effect of 3-D moderator flow configurations on the reactivity of CANDU nuclear reactors. Annals of Nuclear Energy, 99, 136-150. Lien externe

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