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Guy MarleauDépartement de génie physique
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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
Billiet, G., Doligez, X., Marleau, G., Ernoult, M., Hébert, A., & Thiollière, N. (2024). Multi-physics DONJON5 reactor models for improved fuel cycle simulation with CLAS. EPJ Nuclear Sciences & Technologies, 10(5), 2024008 (13 pages). Lien externe
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. Non disponible
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. (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. Non disponible
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, Québec. Non disponible
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). 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. Non disponible
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
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). 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. (2002). HELIOS based incremental cross sections generated using DRAGON. (Rapport technique). 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. (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. (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
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
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
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
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
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. 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
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
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. Non disponible
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. Non disponible
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
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
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. (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
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
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. Non disponible
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., Fevotte, 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
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., & Hébert, A. (mai 2010). The GPT Saga at École Polytechnique [Communication écrite]. 31st CNS Annual Conference, Montréal, Québec. Non disponible
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
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. Non disponible
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. (janvier 2003). Approximate discontinuity factor evaluations in DRAGON [Communication écrite]. 24th annual canadian nuclear society conference, Toronto. 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., & 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. 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., Hébert, A., & Roy, R. (2002). DRAGON programmer's manual. (Rapport technique). 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. (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., & 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). Non disponible
Marleau, G. (octobre 1998). New geometric capabilities of DRAGON [Communication écrite]. 19th Annual Conference of the Canadian Nuclear Society, Toronto, Ontario (Canada). Non disponible
Marleau, G., Sissaoui, M. T., & Rousseau, K. Simulation of Vanadium detectors in DRAGON [Communication écrite]. 19th Annual Conference of the Canadian Nuclear Society. 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. Non disponible
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. (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., & 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
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
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
Petrovic, 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
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
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 2-D simulation of spatial self-shielding effect in SLOWPOKE-2 reactor [Communication écrite]. 24th Nuclear Simulation Symposium, Ottawa, Ontario, 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. 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
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. (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
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. 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., 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., 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
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
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. Non disponible
Sissaoui, M. T., Marleau, G., & Koclas, J. Xenon transients simulation using the reactor code DONJON [Communication écrite]. 19th Annual Conference of the Canadian Nuclear Society. Non disponible
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
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
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
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
