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Journal article (34) Conference paper (100) Book Book chapter Patent Report (2) Thesis

Guy Marleau (136)

  • Journal articles (34)
    • 2019
      • Journal article
        Naceur, A. & Marleau, G. (2019). CANDU-6 operation simulations using accident tolerant cladding candidates. Annals of Nuclear Energy, 124, 472-489. Retrieved from https://doi.org/10.1016/j.anucene.2018.10.026
    • 2018
      • Journal article
        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. Retrieved from https://doi.org/10.1016/j.nucengdes.2018.06.026
      • Journal article
        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. Retrieved from https://doi.org/10.1016/j.nucengdes.2015.10.027
      • Journal article
        Naceur, A. & Marleau, G. (2018). Neutronic analysis for accident tolerant cladding candidates in CANDU-6 reactors. Annals of Nuclear Energy, 113, 147-161. Retrieved from https://doi.org/10.1016/j.anucene.2017.11.016
    • 2017
      • Journal article
        Prabha, H., Karthikeyan, R., Lajoie, M.-A., Marleau, G. & Hebert, A. (2017). Multiplication factors of single pin hexagonal cells and VVER-1000 reactor assembly. Annals of Nuclear Energy, 109, 720-725. Retrieved from https://doi.org/10.1016/j.anucene.2017.04.006
      • Journal article
        Faure, B. & Marleau, G. (2017). Simulation of a sodium fast core: Effect of B1 leakage models on group constant generation. Annals of Nuclear Energy, 99, 484-494. Retrieved from https://doi.org/10.1016/j.anucene.2016.10.002
    • 2016
      • Journal article
        Zadeh, F.M., Etienne, 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. Retrieved from https://doi.org/10.1016/j.anucene.2016.08.004
      • Journal article
        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. Retrieved from https://doi.org/10.1115/1.4030895
      • Journal article
        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. Retrieved from https://doi.org/10.13182/NSE15-60
    • 2015
      • Journal article
        Dion, M. & Marleau, G. (2015). Eigenvalue implicit sensitivity to self-shielding calculations in heterogeneous geometries. Nuclear Science and Engineering, 179(2), 186-198. Retrieved from https://doi.org/10.13182/NSE13-90
      • Journal article
        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. Retrieved from https://doi.org/10.1016/j.anucene.2015.05.022
    • 2014
      • Journal article
        Prabha, H., Marleau, G. & Hebert, A. (2014). Tracking algorithms for multi-hexagonal assemblies (2D and 3D). Annals of Nuclear Energy, 69, 175-182. Retrieved from https://doi.org/10.1016/j.anucene.2014.01.018
    • 2013
      • Journal article
        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. Retrieved from https://doi.org/10.1016/j.nima.2012.10.127
      • Journal article
        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. Retrieved from https://doi.org/10.1155/2013/352757
    • 2012
      • Journal article
        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. Retrieved from https://doi.org/10.5516/NET.08.2010.055
    • 2011
    • 2010
      • Journal article
        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), 1107-1114. Retrieved from https://doi.org/10.1016/j.anucene.2010.04.003
    • 2008
      • Journal article
        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. Retrieved from https://doi.org/10.1016/j.anucene.2007.07.009
      • Journal article
        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), 868-876. Retrieved from https://doi.org/10.1016/j.anucene.2007.09.011
      • Journal article
        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. Retrieved from https://doi.org/10.1016/j.anucene.2007.09.012
    • 2007
      • Journal article
        Assawaroongruengchot, M. & Marleau, G. (2007). Multigroup adjoint transport solution using the method of cyclic characteristics. Nuclear Science and Engineering, 155(1), 37-52. Retrieved from https://doi.org/10.13182/NSE07-A2643
      • Journal article
        Assawaroongruengchot, M. & Marleau, G. (2007). Perturbation Theory Based on the Method of Cyclic Characteristics. Nuclear Science and Engineering, 157(1), 30-50. Retrieved from https://doi.org/10.13182/NSE07-A2711
    • 2006
      • Journal article
        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. Retrieved from https://doi.org/10.1016/j.anucene.2006.06.001
      • Journal article
        Varin, E. & Marleau, G. (2006). CANDU reactor core simulations using fully coupled DRAGON and DONJON calculations. Annals of Nuclear Energy, 33(8), 682-691. Retrieved from https://doi.org/10.1016/j.anucene.2006.03.005
    • 2003
      • Journal article
        Courau, T. & Marleau, G. (2003). Perturbation theory for lattice cell calculations. Nuclear Science and Engineering, 143(1), 19-32. Retrieved from https://doi.org/10.13182/NSE02-11
    • 2002
      • Journal article
        Courau, T. & Marleau, G. (2002). Adjoint and Generalized Adjoint Flux Calculations Using the Collision Probability Technique. Nuclear Science and Engineering, 141(1), 46-54. Retrieved from https://doi.org/10.13182/NSE02-A2265
    • 1999
      • Journal article
        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. Retrieved from https://doi.org/10.13182/NT99-A2942
    • 1997
      • Journal article
        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. Retrieved from https://doi.org/10.1016/S0306-4549(96)00111-9
    • 1996
      • Journal article
        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), 283-285. Retrieved from https://doi.org/10.13182/NSE96-A24163
      • Journal article
        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. Retrieved from https://doi.org/10.13182/NSE96-A24152
    • 1994
      • Journal article
        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. Retrieved from https://doi.org/10.1016/0306-4549(94)90067-1
      • Journal article
        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), 225. Retrieved from https://doi.org/10.13182/NSE94-A19817
  • Conference papers (100)
    • 2018
      • Conference paper
        Marleau, G. & Hébert, A. (2018). DRAGON5 Workshop. Paper presented at the 8th International Conference on Simulation Methods in Nuclear Science and Engineering (8ICSMNSE), Ottawa, ON.
    • 2017
    • 2016
      • Conference paper
        Housseiny Milany, S.R. & Marleau, G. (2016). Application of the transport equation dominant modes in flux mapping. Paper presented at the 36th Annual CNS Conference and 40th CNS-CNA Student Conference - Nuclear in the 21st Century: Global Directions and Canada's Role, Toronto, ON, Canada.
      • Conference paper
        Hébert, A. & Marleau, G. (2016). DRAGON5 Workshop. Paper presented at the Physics of Reactors (PHYSOR 2016): Unifying Theory and Experiments in the 21st Century, Sun Valley, Idaho.
      • Conference paper
        Housseiney Milany, S.R. & Marleau, G. (2016). Implementation of a dominant modes solver in DRAGON. Paper presented at the 36th Annual Conference of the Canadian Nuclear Society and 40th Annual CNS/CNA Student Conference, Toronto, ON.
    • 2015
      • Conference paper
        Hébert, A. & Marleau, G. (2015). DRAGON5 Workshop. Paper presented at the 7th International Conference on Modelling and Simulation in Nuclear Science and Engineering (7ICMSNSE), Ottawa, Canada.
      • Conference paper
        Hébert, A. & Marleau, G. (2015). Workshop 1 : Advancements in DRAGON : New Features of Version 5. Paper presented at the 7th International Conference on Modelling and Simulation in Nuclear Science and Engineering (ICMSNSE), Ottawa, Canada.
    • 2014
      • Conference paper
        Dion, M. & Marleau, G. (2014). A collision probability based method to compute cross sections sensitivities for the subgroup self-shielding technique. Paper presented at the ANS Reactor Physics Topical Meeting (PHYSOR), Kyoto, Japan.
      • Conference paper
        Raouafi, H. & Marleau, G. (2014). A simplified 3D DRAGON simulation of an inclined reactivity control device for the Canadian-SCWR. Paper presented at the 19th Pacific Basin Nuclear Conference (PBNC 2014), Vancouver, British Columbia, Canada.
      • Conference paper
        Bejaoui, N. & Marleau, G. (2014). Modelling of CANDU-SCWR unit cell with DRAGON: from Cartesian to hexagonal geometry. Paper presented at the 2014 Canada-China Conference on Advanced Reactor Development (CCCARD-2014), Niagara Falls, Ontario Canada.
    • 2013
      • Conference paper
        Lajoie, M.A., Fevotte, F. & Marleau, G. (2013). A generalization of 3D prismatic characteristics along a nonuniform projection mesh. Paper presented at the Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2013, SNA & MC 2013, Paris, France (8 pages). Retrieved from https://doi.org/10.1051/snamc/201402203
      • Conference paper
        Dion, M. & Marleau, G. (2013). Resonance self-shielding effects on eigenvalue sensitivity. Paper presented at the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2013, Sun Valley, ID, United states (pp. 148-159).
    • 2012
      • Conference paper
        Camand, C. & Marleau, G. (2012). Comparative study of DRAGON and TRIPOLI for a PWR assembly. Paper presented at the 24th Nuclear Simulation Symposium, Ottawa, Ontario, Canada.
      • Conference paper
        Chambon, R. & Marleau, G. (2012). Comparison of point kinetics, improved quasistatic and theta method as space-time kinetics solvers in donjon-3 simulations. Paper presented at the International Conference on the Physics of Reactors 2012: Advances in Reactor Physics, PHYSOR 2012, Knoxville, TN, United states (pp. 3175-3187).
      • Conference paper
        Harrisson, G. & Marleau, G. (2012). Computation of a Canadian SCWR unit cell with deterministic and Monte Carlo codes. Paper presented at the International Conference on the Physics of Reactors 2012: Advances in Reactor Physics, PHYSOR 2012, Knoxville, TN, United states (pp. 1344-1354).
      • Conference paper
        Prabha, H. & Marleau, G. (2012). Computation of neutron fluxes in clusters of fuel pins arranged in hexagonal assemblies (2D and 3D). Paper presented at the International Conference on the Physics of Reactors 2012: Advances in Reactor Physics, PHYSOR 2012, Knoxville, TN, United states (pp. 2048-2059).
      • Conference paper
        Harrisson, G. & Marleau, G. (2012). 2-D and 3-D evaluation of neutronic properties along a caadian SCWR fuel channel. Paper presented at the 3rd China-Canada Joint Workshop on Supercritical Water-Cooled Reactors (CCSC), Xi'an, Shaanxi, China.
      • Conference paper
        Chambon, R. & Marleau, G. (2012). DDGui, a new and fast way to analyse DRAGON and DONJON code results. Paper presented at the International Conference on the Physics of Reactors 2012: Advances in Reactor Physics, PHYSOR 2012, Knoxville, TN, United states (pp. 346-360).
      • Conference paper
        Raouafi, H. & Marleau, G. (2012). DRAGON and SERPENT 2-D modelling of the SLOWPOKE-2 reactor at École Polytechnique Montréal. Paper presented at the 24th Nuclear Simulation Symposium, Ottawa, Ontario, Canada.
      • Conference paper
        Raouafi, H. & Marleau, G. (2012). DRAGON 2-D simulation of spatial self-shielding effect in SLOWPOKE-2 reactor. Paper presented at the 24th Nuclear Simulation Symposium, Ottawa, Ontario, Canada.
      • Conference paper
        Bejaoui, N. & Marleau, G. (2012). DRAGON simulation of a radial PWR reflector. Paper presented at the 24th Nuclear Simulation Symposium, Ottawa, Ontario, Canada.
      • Conference paper
        St-Aubin, E. & Marleau, G. (2012). Modeling CANDU-6 liquid zone controllers for effects of thorium-based fuels. Paper presented at the International Conference on the Physics of Reactors 2012: Advances in Reactor Physics, PHYSOR 2012, Knoxville, TN, United states (pp. 2096-2107).
      • Conference paper
        Adouki, P. & Marleau, G. (2012). Neutronics/thermalhydraulics coupling in a CANDU SCWR. Paper presented at the 3rd China-Canada Joint Workshop on Supercritical Water-Cooled Reactors (CCSC), Xi'an, Shaanxi, China.
    • 2011
      • Conference paper
        St-Aubin, E. & Marleau, G. (2011). An optimization scheme for selecting alternative fuels in CANDU-6 reactor. Paper presented at the 32nd Annual Conference of the CNS, Niagara Falls, Canada.
      • Conference paper
        St-Aubin, E. & Marleau, G. (2011). CANDU-6 devices reactivity worth adjustement for advanced fuel cycles. Paper presented at the 2nd International Conference on Physics and Technology of Reactors and Applications, Fez, Morocco.
      • Conference paper
        Harrisson, G. & Marleau, G. (2011). Modeling of a 3-D SCWR unit cell. Paper presented at the 32nd Annual Conference of the CNS, Niagara Falls, Canada.
      • Conference paper
        Laville, C., Marleau, G., Ivanova, T., Bernard, F. & Richet, Y. (2011). Sensitivity calculations for UACSA beanchmark phase III by IRSN. Paper presented at the International Conference on Nuclear Criticality, Edinburgh, UK.
      • Conference paper
        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. Paper presented at the 32nd Annual Conference of the CNS, Niagara Falls, Canada.
    • 2010
      • Conference paper
        Lajoie, M.A., Marleau, G., Martin, N. & Hebert, A. (2010). Application of 3D collision probability method to VHTR spherical geometries. Paper presented at the International Conference on Advances in Reactor Physics to Power the Nuclear Reanissance (PHYSOR 2010), Pittsburgh, Pennsylvania.
      • Conference paper
        Lajoie, M.A. & Marleau, G. (2010). Application of the full 3-D collision probability method to randomly distributes spherical fuel elements. Paper presented at the 31st annual Conference of the CNS, Montréal, Québec.
      • Conference paper
        Altiparmakow, D., Shen, W., Marleau, G. & Rouben, B. (2010). Evolution of computer codes for CANDU analysis. Paper presented at the PHYSOR Topical Meeting, Pittsburgh, Pennsylvania.
      • Conference paper
        Harrisson, G. & Marleau, G. (2010). Models for resonance self-shielding calculation in neutronic analysis of the CANDU-SCWR fuel channel. Paper presented at the 31st annual Conference of the CNS, Montréal, Québec.
      • Conference paper
        Roy, R., Marleau, G. & Hebert, A. (2010). Rudi Stamm'ler contributions and DRAGON. Paper presented at the International Conference on Advances in Reactor Physics to Power the Nuclear Reanissance (PHYSOR 2010), Pittsburgh, Pennsylvania.
      • Conference paper
        Marleau, G. & Veyret, P. (2010). Simulating sample irradiation in the SLOWPOKE reactor using the lattice code DRAGON. Paper presented at the Technical Meeting on Low-Power Critical Facilities and Small Reactors, Ottawa, Canada.
      • Conference paper
        Marleau, G. & Hebert, A. (2010). The GPT Saga at École Polytechnique. Paper presented at the 31st CNS Annual Conference, Montréal, Québec.
      • Conference paper
        Marleau, G., Kennedy, G. & Chilian, C. (2010). Training new operators for the SLOWPOKE reactor at École Polytechnique : Theory and practice. Paper presented at the Technical Meeting on Low-Power Critical Facilities and Small Reactors, Ottawa, Canada.
    • 2009
      • Conference paper
        Dion, M. & Marleau, G. (2009). Comparison of probabilistic and deterministic error propagation calculations in DRAGON. Paper presented at the International Conference on Mathematics, Computational Methods and Reactor Physics 2009, Saratoga Springs, NY, United states (pp. 2934-2945).
      • Conference paper
        Alcaro, F., Dulla, S., Marleau, G., Mund, E. & Ravetto, P. (2009). Development of dynamic models for neutron transport calculations. Paper presented at the XXI International Conference on Transport Theroy, Torino, Italy.
      • Conference paper
        Leroyer, H. & Marleau, G. (2009). Dragon evaluation of the effect of heterogeneous environment on PWR assemblies. Paper presented at the International Conference on Mathematics, Computational Methods and Reactor Physics 2009, Saratoga Springs, NY, United states (pp. 763-772).
      • Conference paper
        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+. Paper presented at the International Conference on Mathematics, Computational Methods and Reactor Physics, Saratoga Springs, NY, United states (pp. 2306-2316).
      • Conference paper
        Bidaud, A., Marleau, G. & Noblat, E. (2009). Nuclear data uncertainty analysis using the coupling of DRAGON with SUSD3D. Paper presented at the International Conference on Mathematics, Computational Methods and Reactor Physics 2009, Saratoga Springs, NY, United states (pp. 2348-2357).
      • Conference paper
        Courau, T., Sjoden, G. & Marleau, G. (2009). PWR assembly transport calculation: A validation benchmark using DRAGON, PENTRAN, and MCNP. Paper presented at the International Conference on Mathematics, Computational Methods and Reactor Physics 2009, Saratoga Springs, NY, United states (pp. 626-638).
      • Conference paper
        Popov, A.V., Assawaroongruengchot, M., Marleau, G., Hebert, A. & Karthikeyan, R. (2009). Validating models for coolant void reactivity evaluation in CANDU Generation III+. Paper presented at the International Conference on Mathematics, Computational Methods and Reactor Physics 2009, Saratoga Springs, NY, United states (pp. 2703-2710).
    • 2008
      • Conference paper
        Martin, N., Marleau, G. & Hebert, A. (2008). A premilinary study of the OECD/NEA 3D transport problem using the lattice code DRAGON. Paper presented at the Symposium on Simulation Methods in Nuclear Engineering, Ottawa, Canada.
      • Conference paper
        Le Tellier, R., Marleau, G. & Hebert, A. (2008). Burn-up dependence of coolant void reactivity for ACR-1000 cell. Paper presented at the International Conference on the Physics of Reactors, Interlaken, Switzerland.
      • Conference paper
        V., P.A., Chambon, R.P., Le Tellier, R., Marleau, G. & Hebert, A. (2008). Models for coolant void reactivity evaluation in CANDU Generation II and III+. Paper presented at the International Conference on the Physics of Reactors, Interlaken, Switzerland.
      • Conference paper
        Popov, A.V., Marleau, G. & Olkehnovitch, A. (2008). The third generation of heavywater moderated reactors. Paper presented at the 16th Pacific Basin Nuclear Conference, Aomori, Japan.
    • 2007
      • Conference paper
        Le Mer, J. & Marleau, G. (2007). Dragon evaluation of the benchmark for the Doppler reactivity defect. Paper presented at the Joint International Topical Meeting on Mathematics and Computations and Supercomputing in Nuclear Applications, M and C + SNA 2007, Monterey, CA, United States (pp. 12).
    • 2006
      • Conference paper
        Dahmani, M., Marleau, G. & Varin, É. (2006). Effect of Burnup on ACR-700 3-D Reactivity Devices Cross Sections. Paper presented at the PHYSOR-2006, Vancouver, Canada.
      • Conference paper
        Assawaroongruengchot, M. & Marleau, G. (2006). Generalized Perturbation Theory Based on the Method of Cyclic Characteristics. Paper presented at the PHYSOR-2006, Vancouver, Canada (pp. 2574-2583).
      • Conference paper
        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. Paper presented at the PHYSOR-2006, Vancouver, Canada.
      • Conference paper
        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. Paper presented at the Advances in Nuclear Analysis and Simulation (PHYSOR 2006), Vancouver, Canada (pp. 558-567).
    • 2005
      • Conference paper
        Le Tellier, R. & Hébert, A. (2005). Application of the characteristics method combined with advanced self shielding models to an ACR-type cell. Paper presented at the 26th Annual CNS Conference (CSN 2005), Toronto, ON.
      • Conference paper
        Karthikeyan, R., Hébert, A. & Marleau, G. (2005). Depleting a CANDU-6 fuel assembly using detailed burnup data and reactionwise energy release. Paper presented at the 26th Annual CNS Conference (CSN 2005), Toronto, ON.
      • Conference paper
        Karthikeyan, R., Hébert, A. & Marleau, G. (2005). Effects of advanced self shielding and burnup models on fuel temperature coefficient estimation for a Candu-6 assembly. Paper presented at the International Topical Meeting on Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications (M&C 2005), Avignon, France.
      • Conference paper
        Varin, E. & Marleau, G. (2005). Validating the history-bases method in DRAGON/DONJON using G2 core follow-up. Paper presented at the CNS 2005 Annuel Conference, Toronto.
    • 2004
      • Conference paper
        Marleau, G. (2004). CANDU adjuster rods incremental cross sections evaluation: a perturbative approach. Paper presented at the PHYSOR 2004 - The physics of fuel cycles and advanced nuclear systems: global developments, Chicago, illinois, USA.
      • Conference paper
        Dufour, P., Marleau, G. & Koclas, J. (2004). Computation of surface fluxes in the lattice code DRAGON. Paper presented at the 25th annual CNS conference - Nuclear energy: meeting the challenges, Toronto, Ontario, Canada.
      • Conference paper
        Varin, E. & Marleau, G. (2004). First attemp at a CANDU-6 core tracking using the coupled DRAGON/DONJON calculations. Paper presented at the 6th international conference on simulation methods in nuclear engineering, Montréal, Québec.
    • 2003
      • Conference paper
        Marleau, G. (2003). Approximate discontinuity factor evaluations in DRAGON. Paper presented at the 24th annual canadian nuclear society conference, Toronto.
      • Conference paper
        Dufour, P., Koclas, J. & Marleau, G. (2003). Reactor power computation using a model with three pseudo-fission products. Paper presented at the 24th annual canadian nuclear society conference, Toronto.
      • Conference paper
        Marleau, G. & Varin, É. (2003). Transport analyses of 2-D CANDU diffusion calculations. Paper presented at the American nuclear society topical meeting in mathematics and computations, Gatlinburg, Tennessee, USA.
      • Conference paper
        Varin, E., Marleau, G. & Chambon, R. (2003). Transport-diffusion coupling for CANDU reactor core follow-up. Paper presented at the International conference on supercomputing in nuclear applications SNA'2003, Paris, France.
    • 2002
      • Conference paper
        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. Paper presented at the 22nd canadian nuclear society simulation symposium, Ottawa.
      • Conference paper
        Marleau, G. & Varin, E. (2002). Coolant void reactivity in a CANDU: a 2-D transport/diffusion comparison. Paper presented at the 22nd canadian nuclear society simulation symposium, Ottawa.
      • Conference paper
        Marleau, G. & Foissac, F. (2002). DRAGON analysis of MOX fueled VVER cell benchmarks. Paper presented at the 23rd annual canadian nuclear society conference, Toronto.
      • Conference paper
        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. Paper presented at the 22nd canadian nuclear society simulation symposium, Ottawa.
      • Conference paper
        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. Paper presented at the 22nd canadian nuclear society simulation symposium, Ottawa.
      • Conference paper
        Marleau, G. (2002). Verification of DRAGON: progress and lessons learned. Paper presented at the 23rd annual canadian nuclear society conference, Toronto.
    • 2001
      • Conference paper
        Courau, T. & Marleau, G. (2001). Generalized perturbation theory in DRAGON: application to CANDU cell calculations. Paper presented at the 33nd annual conference of the canadian nuclear society, Torontp, ON, Canada (pp. 12).
      • Conference paper
        Courau, T. & Marleau, G. (2001). Generalized perturbation theory in DRAGON: application to PWR assembly calculations. Paper presented at the M&C 2001 american nuclear society international meeting on mathematical methods for nuclear applications, Salt Lake City, UT, USA (pp. 14).
    • 2000
      • Conference paper
        Courau, T. & Marleau, G. (2000). Calculating adjoint fluxes in the code DRAGON using the collision probability method. Paper presented at the ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium (PHYSOR 2000), Pittsburgh, USA (pp. 822-833).
      • Conference paper
        Roy, R. & Marleau, G. (2000). DRAGON solutions for benchmark BWR lattice cell problem. Paper presented at the PHYSOR 2000 american nuclear society international topical meeting, advances in reactor physics and mathematics and computation into the next millenium, Pittsburgh, PA, USA (pp. 11).
    • 1999
      • Conference paper
        Marleau, G. (1999). Coherent anistropic scattering homogenization in the B1 leakage model. Paper presented at the M&C 1999 mathematics and computation, reacto physics and environmental analysis in nucleaar applications, Madrid, Spain (pp. 909-918).
      • Conference paper
        Boubcher, M., Marleau, G. & Rozon, D. (1999). Development of an isotopic depletion method for reactor core calculations. Paper presented at the Communicating the nuclear advantage. 39th Annual Canadian Nuclear Association Conference & 20th Annual Canadian Nuclear Society Conference, Montréal, Québec (pp. 72-83).
      • Conference paper
        Benjaafar, H. & Marleau, G. (1999). Generation of microscopic pseudo fission-products properties. Paper presented at the Communicating the nuclear advantage. 39th Annual Canadian Nuclear Association Conference & 20th Annual Canadian Nuclear Society Conference, Montréal, Québec (pp. 123-133).
    • 1998
      • Conference paper
        Marleau, G. (1998). Fine mesh 3-D collision probability calculations using the lattice code DRAGON. Paper presented at the Proc. Int. Conf. Phys. Nucl. Sci. Technol, Long Island, USA (pp. 523-530).
      • Conference paper
        Marleau, G. & Debos, E. (1998). Homogenization of linearly anisotropic scattering cross sections in a consistent B1 heterogeneous leakage model. Paper presented at the 19th Annual Conference of the Canadian Nuclear Society, Toronto, Ontario (Canada).
      • Conference paper
        Marleau, G. (1998). New geometric capabilities of DRAGON. Paper presented at the 19th Annual Conference of the Canadian Nuclear Society, Toronto, Ontario (Canada).
      • Conference paper
        Shen, W., Rozon, D. & Marleau, G. (1998). Parametric analysis of Doppler coefficient of reactivity in DUPIC fuel by DRAGON. Paper presented at the 19th Annual Conference of the Canadian Nuclear Society (pp. 3C1.1-3C1.8).
      • Conference paper
        Boubcher, M., Marleau, G. & Rozon, D. (1998). Pseudo-isotopes generation for the 235U and 238U depletion chains. Paper presented at the 19th Annual Conference of the Canadian Nuclear Society, Toronto, Ontario (Canada).
      • Conference paper
        Marleau, G., Sissaoui, M.T. & Rousseau, K. (1998). Simulation of Vanadium detectors in DRAGON. Paper presented at the 19th Annual Conference of the Canadian Nuclear Society (pp. 7.1-7.11).
      • Conference paper
        Sissaoui, M.T., Marleau, G. & Koclas, J. (1998). Xenon transients simulation using the reactor code DONJON. Paper presented at the 19th Annual Conference of the Canadian Nuclear Society (pp. 4C6.1-4C6.13).
    • 1997
      • Conference paper
        Sissaoui, M.T., Marleau, G. & Rozon, D. (1997). Accounting for actinide burnup history in CANDU reactor simulations. Paper presented at the Advances in nuclear fuel management II : topical meeting (pp. 9/21-9/29).
      • Conference paper
        Marleau, G., Noceir, S., Roy, R. & Rozon, D. (1997). Dragon modelling of the SLOWPOKE-2 reactor at Ecole Polytechnique. Paper presented at the 1997 Canadian Nuclear Society Conference, Toronto, Can.
      • Conference paper
        Marleau, G. & Grammont, X. (1997). Fewgroup burnup calculations using time dependent microscopic cross sections. Paper presented at the 1997 Canadian Nuclear Society Conference, Toronto, Can.
      • Conference paper
        Kennedy, G. & Marleau, G. (1997). Refuelling the SLOWPOKE-2 reactor at Ecole Polytechnique: Procedure and proposed experiments. Paper presented at the 1997 Canadian Nuclear Society Conference, Toronto, Can.
    • 1996
      • Conference paper
        Marleau, G. (1996). A validation of DRAGON based on lattice experiments. Paper presented at the 5th International Conference on Simulation Methods in Nuclear Engineering, Montréal, Québec (pp. P7/1-7/14).
    • 1995
      • Conference paper
        Marleau, G. & Milgram, M.S. (1995). A DRAGON-MCNP comparison of axial diffusion subcoefficients. Paper presented at the 1995 Annual Meeting of American Nuclear Society, Philadelphia, PA. (Published in Transactions of the American Nuclear Society, 72, 163-164).
      • Conference paper
        Sissaoui, M.T. & Marleau, G. (1995). Application of the feedback model for the history base using DRAGON. Paper presented at the 19. CNS simulation symposium, Hamilton (Canada) (pp. 12).
      • Conference paper
        Hébert, A., Marleau, G. & Roy, R. (1995). Application of the lattice code DRAGON to CANDU analysis. Paper presented at the Annual meeting of the American Nuclear Society (ANS), Philadelphia, Penn. (Published in Transactions of the American Nuclear Society, 72, 335-337).
      • Conference paper
        Hébert, A., Marleau, G. & Roy, R. (1995). Application of the lattice code DRAGON to CANDU reactor analysis. Paper presented at the Annual Meeting and the Embedded Topical Meeting on Computer-Based Human Support Systems of American Nuclear Society (ANS 1995), Philadelphia, PA.
      • Conference paper
        Petrovic, I., Benoist, P. & Marleau, G. (1995). A simplified heterogeneous B1 model with isotropically-reflected neutrons on assembly boundary. Paper presented at the International Conference on Mathematics and Computation, Reactor Physics, and Environmental Analyses, Portland, OR, USA (pp. 792-801).
      • Conference paper
        Marleau, G. & Milgram, M.S. (1995). Dragon-MCNP comparison of void reactivity calculations. Paper presented at the 1995 16th Annual Conference of the Canadian Nuclear Society, Saskatoon, Can (pp. 8).
    • 1994
      • Conference paper
        Petrovic, I., Benoist, P. & Marleau, G. (1994). A simplified heterogeneous B1 model with isotropically-reflected neutrons on assembly boundary. Paper presented at the 1994 nuclear simulation symposium, Pembroke (Canada) (pp. 45-54).
      • Conference paper
        Marleau, G., Roy, R. & Hébert, A. (1994). Finite element solution to the transport equation. Paper presented at the 15th Annual Conference of the Canadian Nuclear Society (CSN 1994), Montréal, Québec (pp. 3B/13).
      • Conference paper
        Qaddouri, A., Roy, R., Marleau, G., Goulard, B. & Mayrand, M. (1994). Multigroup flux solvers on parallel architecture. Paper presented at the 15th Annual Conference of the Canadian Nuclear Society, Montréal, Québec.
      • Conference paper
        Marleau, G., Roy, R. & Arsenault, B. (1994). Simulation of reactivity control devices in a CANDU-6 reactor using DRAGON. Paper presented at the 1994 nuclear simulation symposium, Pembroke (Canada) (pp. 113-121).
      • Conference paper
        Varin, E., Marleau, G. & Roy, R. (1994). Towards the generation of a consistent reactor cross-section database for CANDU-6 using DRAGON. Paper presented at the 1994 nuclear simulation symposium, Pembroke (Canada) (pp. 34-43).
  • Reports (2)
    • 2002
      • Report
        Marleau, G., Hébert, A. & Roy, R. (2002). DRAGON programmer's manual. École Polytechnique.
      • Report
        Courau, T. & Marleau, G. (2002). HELIOS based incremental cross sections generated using DRAGON. École Polytechnique.