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Guy MarleauDepartment of Engineering Physics
Profile in the Directory of Experts of Polytechnique Montréal
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Adouki, P., & Marleau, G. (2012, April). Neutronics/thermalhydraulics coupling in a CANDU SCWR [Paper]. 3rd China-Canada Joint Workshop on Supercritical Water-Cooled Reactors (CCSC), Xi'an, Shaanxi, China. Unavailable
Altiparmakow, D., Shen, W., Marleau, G., & Rouben, B. (2010, May). Evolution of computer codes for CANDU analysis [Paper]. PHYSOR Topical Meeting, Pittsburgh, Pennsylvania. External link
Alcaro, F., Dulla, S., Marleau, G., Mund, E., & Ravetto, P. (2009, July). Development of dynamic models for neutron transport calculations [Paper]. XXI International Conference on Transport Theroy, Torino, Italy. External link
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. External link
Assawaroongruengchot, M., & Marleau, G. (2007). Multigroup adjoint transport solution using the method of cyclic characteristics. Nuclear Science and Engineering, 155(1), 37-52. External link
Assawaroongruengchot, M., & Marleau, G. (2007). Perturbation Theory Based on the Method of Cyclic Characteristics. Nuclear Science and Engineering, 157(1), 30-50. External link
Assawaroongruengchot, M., & Marleau, G. (2006, September). Generalized Perturbation Theory Based on the Method of Cyclic Characteristics [Paper]. PHYSOR-2006, Vancouver, Canada. Unavailable
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). Available
Bejaoui, N., & Marleau, G. (2014, April). Modelling of CANDU-SCWR unit cell with DRAGON: from Cartesian to hexagonal geometry [Paper]. 2014 Canada-China Conference on Advanced Reactor Development (CCCARD-2014), Niagara Falls, Ontario Canada. Unavailable
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. External link
Bejaoui, N., & Marleau, G. (2012, October). DRAGON simulation of a radial PWR reflector [Paper]. 24th Nuclear Simulation Symposium, Ottawa, Ontario, Canada. Unavailable
Bentoumi, G., Dai, X., Ho, A., Jonkmans, G., Li, L., & Marleau, G. (2011, June). Simulation and design of a neutron detector based on Boron-Loaded linear alkyl benzene (LAB) liquid scintillator [Paper]. 32nd Annual Conference of the CNS, Niagara Falls, Canada. Unavailable
Bidaud, A., Marleau, G., & Noblat, E. (2009, May). Nuclear data uncertainty analysis using the coupling of DRAGON with SUSD3D [Paper]. International Conference on Mathematics, Computational Methods and Reactor Physics 2009, Saratoga Springs, NY, United states. Unavailable
Boubcher, M., Marleau, G., & Rozon, D. (1999, May). Development of an isotopic depletion method for reactor core calculations [Paper]. Communicating the nuclear advantage. 39th Annual Canadian Nuclear Association Conference & 20th Annual Canadian Nuclear Society Conference, Montréal, Québec. Unavailable
Benjaafar, H., & Marleau, G. (1999, May). Generation of microscopic pseudo fission-products properties [Paper]. Communicating the nuclear advantage. 39th Annual Canadian Nuclear Association Conference & 20th Annual Canadian Nuclear Society Conference, Montréal, Québec. Unavailable
Boubcher, M., Marleau, G., & Rozon, D. (1998, October). Pseudo-isotopes generation for the ²³⁵U and ²³⁸U depletion chains [Paper]. 19th Annual Conference of the Canadian Nuclear Society, Toronto, Ontario (Canada). Unavailable
Camand, C., & Marleau, G. (2012, October). Comparative study of DRAGON and TRIPOLI for a PWR assembly [Paper]. 24th Nuclear Simulation Symposium, Ottawa, Ontario, Canada. Unavailable
Chambon, R., & Marleau, G. (2012, April). Comparison of point kinetics, improved quasistatic and theta method as space-time kinetics solvers in donjon-3 simulations [Paper]. International Conference on the Physics of Reactors 2012: Advances in Reactor Physics, PHYSOR 2012, Knoxville, TN, United states. Unavailable
Chambon, R., & Marleau, G. (2012, April). DDGui, a new and fast way to analyse DRAGON and DONJON code results [Paper]. International Conference on the Physics of Reactors 2012: Advances in Reactor Physics, PHYSOR 2012, Knoxville, TN, United states. Unavailable
Courau, T., Sjoden, G., & Marleau, G. (2009, May). PWR assembly transport calculation: A validation benchmark using DRAGON, PENTRAN, and MCNP [Paper]. International Conference on Mathematics, Computational Methods and Reactor Physics 2009, Saratoga Springs, NY, United states. Unavailable
Courau, T., & Marleau, G. (2003). Perturbation theory for lattice cell calculations. Nuclear Science and Engineering, 143(1), 19-32. External link
Courau, T., & Marleau, G. (2002). Adjoint and Generalized Adjoint Flux Calculations Using the Collision Probability Technique. Nuclear Science and Engineering, 141(1), 46-54. External link
Courau, T., & Marleau, G. (2002). HELIOS based incremental cross sections generated using DRAGON. (Technical Report). Unavailable
Courau, T., & Marleau, G. (2001, January). Generalized perturbation theory in DRAGON: application to CANDU cell calculations [Paper]. 33nd annual conference of the canadian nuclear society, Toronto, ON, Canada. Unavailable
Courau, T., & Marleau, G. (2001, January). Generalized perturbation theory in DRAGON: application to PWR assembly calculations [Paper]. M&C 2001 american nuclear society international meeting on mathematical methods for nuclear applications, Salt Lake City, UT, USA. Unavailable
Courau, T., & Marleau, G. (2000, May). Calculating adjoint fluxes in the code DRAGON using the collision probability method [Paper]. ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium (PHYSOR 2000), Pittsburgh, USA. Unavailable
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. External link
Dion, M., & Marleau, G. (2015). Eigenvalue implicit sensitivity to self-shielding calculations in heterogeneous geometries. Nuclear Science and Engineering, 179(2), 186-198. External link
Dion, M., & Marleau, G. (2014, September). A collision probability based method to compute cross sections sensitivities for the subgroup self-shielding technique [Paper]. ANS Reactor Physics Topical Meeting (PHYSOR), Kyoto, Japan. Unavailable
Dion, M., & Marleau, G. (2013, May). Resonance self-shielding effects on eigenvalue sensitivity [Paper]. International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2013, Sun Valley, ID, United states. Unavailable
Dion, M., & Marleau, G. (2009, May). Comparison of probabilistic and deterministic error propagation calculations in DRAGON [Paper]. International Conference on Mathematics, Computational Methods and Reactor Physics 2009, Saratoga Springs, NY, United states. Unavailable
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. External link
Dahmani, M., Marleau, G., & Varin, É. (2006, September). Effect of Burnup on ACR-700 3-D Reactivity Devices Cross Sections [Paper]. PHYSOR-2006, Vancouver, Canada. Unavailable
Dufour, P., Marleau, G., & Koclas, J. (2004, June). Computation of surface fluxes in the lattice code DRAGON [Paper]. 25th annual CNS conference - Nuclear energy: meeting the challenges, Toronto, Ontario, Canada. Unavailable
Dufour, P., Koclas, J., & Marleau, G. (2003, January). Reactor power computation using a model with three pseudo-fission products [Paper]. 24th annual canadian nuclear society conference, Toronto. Unavailable
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. Available
Housseiny Milany, S. R., & Marleau, G. (2016, June). Application of the transport equation dominant modes in flux mapping [Paper]. 36th Annual CNS Conference and 40th CNS-CNA Student Conference - Nuclear in the 21st Century: Global Directions and Canada's Role, Toronto, ON, Canada. Unavailable
Hébert, A., & Marleau, G. (2016, May). DRAGON5 Workshop [Paper]. Physics of Reactors (PHYSOR 2016): Unifying Theory and Experiments in the 21st Century, Sun Valley, Idaho. Unavailable
Housseiney Milany, S. R., & Marleau, G. (2016, June). Implementation of a dominant modes solver in DRAGON [Paper]. 36th Annual Conference of the Canadian Nuclear Society and 40th Annual CNS/CNA Student Conference, Toronto, ON. Unavailable
Hébert, A., & Marleau, G. (2015, October). DRAGON5 Workshop [Paper]. 7th International Conference on Modelling and Simulation in Nuclear Science and Engineering (7ICMSNSE), Ottawa, Canada. Unavailable
Hébert, A., & Marleau, G. (2015, October). Workshop 1 : Advancements in DRAGON : New Features of Version 5 [Paper]. 7th International Conference on Modelling and Simulation in Nuclear Science and Engineering (ICMSNSE), Ottawa, Canada. Unavailable
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. Available
Harrisson, G., & Marleau, G. (2012, April). 2-D and 3-D evaluation of neutronic properties along a caadian SCWR fuel channel [Paper]. 3rd China-Canada Joint Workshop on Supercritical Water-Cooled Reactors (CCSC), Xi'an, Shaanxi, China. Unavailable
Harrisson, G., & Marleau, G. (2012, April). Computation of a Canadian SCWR unit cell with deterministic and Monte Carlo codes [Paper]. International Conference on the Physics of Reactors 2012: Advances in Reactor Physics, PHYSOR 2012, Knoxville, TN, United states. Unavailable
Harrisson, G., & Marleau, G. (2011, June). Modeling of a 3-D SCWR unit cell [Paper]. 32nd Annual Conference of the CNS, Niagara Falls, Canada. Unavailable
Harrisson, G., & Marleau, G. (2010, May). Models for resonance self-shielding calculation in neutronic analysis of the CANDU-SCWR fuel channel [Paper]. 31st annual Conference of the CNS, Montréal, Québec. Unavailable
Hébert, A., Marleau, G., & Roy, R. (1995, June). Application of the lattice code DRAGON to CANDU analysis [Paper]. Annual meeting of the American Nuclear Society (ANS), Philadelphia, Penn.. Published in Transactions of the American Nuclear Society, 72. Unavailable
Hébert, A., Marleau, G., & Roy, R. (1995, June). Application of the lattice code DRAGON to CANDU reactor analysis [Paper]. Annual Meeting and the Embedded Topical Meeting on Computer-Based Human Support Systems of American Nuclear Society (ANS 1995), Philadelphia, PA. Unavailable
Inzirillo, F., Brighenti, A., Cammi, A., Graziano, L., Hébert, A., Marleau, G., Santandrea, S., & Vezzoni, B. (2024, April). Towards 2D reference deterministic calculations in support of industrial model verification and advanced reflector modeling setup [Paper]. 2024 International Conference on Physics of Reactors (PHYSOR 2024), San Francisco, CA, USA. External link
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. External link
Karthikeyan, R., Hébert, A., & Marleau, G. (2005, June). Depleting a CANDU-6 fuel assembly using detailed burnup data and reactionwise energy release [Paper]. 26th Annual CNS Conference (CSN 2005), Toronto, ON. Unavailable
Karthikeyan, R., Hébert, A., & Marleau, G. (2005, September). Effects of advanced self shielding and burnup models on fuel temperature coefficient estimation for a Candu-6 assembly [Paper]. International Topical Meeting on Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications (M&C 2005), Avignon, France. Unavailable
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. External link
Kennedy, G. G., & Marleau, G. (1997, June). Refuelling the SLOWPOKE-2 reactor at École Polytechnique: Procedure and proposed experiments [Paper]. 1997 Canadian Nuclear Society Conference, Toronto, Can. Unavailable
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). External link
Liegeard, C., Calloo, A., Marleau, G., & Girardi, E. (2017, April). Impact of photon transport on power distribution [Paper]. International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering (M&C 2017), Jeju, Korea (8 pages). External link
Lajoie, M.-A., Févotte, F., & Marleau, G. (2013, October). A generalization of 3D prismatic characteristics along a nonuniform projection mesh [Paper]. Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2013, SNA & MC 2013, Paris, France (8 pages). External link
Laville, C., Marleau, G., Ivanova, T., Bernard, F., & Richet, Y. (2011, September). Sensitivity calculations for UACSA benchmark phase III by IRSN [Paper]. International Conference on Nuclear Criticality, Edinburgh, UK. Unavailable
Lajoie, M. A., Marleau, G., Martin, N., & Hébert, A. (2010, May). Application of 3D collision probability method to VHTR spherical geometries [Paper]. International Conference on Advances in Reactor Physics to Power the Nuclear Renaissance (PHYSOR 2010), Pittsburgh, Pennsylvania. Unavailable
Lajoie, M. A., & Marleau, G. (2010, May). Application of the full 3-D collision probability method to randomly distributes spherical fuel elements [Paper]. 31st annual Conference of the CNS, Montréal, Québec. Unavailable
Leroyer, H., & Marleau, G. (2009, May). Dragon evaluation of the effect of heterogeneous environment on PWR assemblies [Paper]. International Conference on Mathematics, Computational Methods and Reactor Physics 2009, Saratoga Springs, NY, United states. Unavailable
Le Tellier, R., Marleau, G., & Hébert, A. (2023, September). Burn-up dependence of coolant void reactivity for ACR-1000 cell [Paper]. International Conference on the Physics of Reactors, Interlaken, Switzerland. Unavailable
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. External link
Le Mer, J., & Marleau, G. (2007, April). Dragon evaluation of the benchmark for the Doppler reactivity defect [Paper]. Joint International Topical Meeting on Mathematics and Computations and Supercomputing in Nuclear Applications, M and C + SNA 2007, Monterey, CA, United States. External link
Le Tellier, R., Hébert, A., & Marleau, G. (2006, September). The Implementation of a 3-D Characteristics Solver for the Generation of Incremental Cross Section for Reactivity Devices in a CANDU Reactor [Paper]. Advances in Nuclear Analysis and Simulation (PHYSOR 2006), Vancouver, Canada. Unavailable
Musongela, M., & Marleau, G. (2022). Generalization of the tibere B1 leakage model to the method of characteristics. Annals of Nuclear Energy, 174, 9 pages. External link
Marleau, G., & Hébert, A. (2018, October). DRAGON5 Workshop [Paper]. 8th International Conference on Simulation Methods in Nuclear Science and Engineering (8ICSMNSE), Ottawa, ON. Unavailable
Milany, S. R. H., & Marleau, G. (2017, April). A hybrid stochastic deterministic approach for full core neutronics [Paper]. International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering (M&C 2017), Jeju, Korea (8 pages). External link
Marleau, G., & Chambon, R. (2011). Fukushima, des notions techniques aux enseignements pratiques en passant par les conséquences. Physique au Canada, 67(4), 267-271. External link
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. External link
Marleau, G., & Hébert, A. (2010, May). The GPT Saga at École Polytechnique [Paper]. 31st CNS Annual Conference, Montréal, Québec. Unavailable
Marleau, G., & Veyret, P. (2010, November). Simulating sample irradiation in the SLOWPOKE reactor using the lattice code DRAGON [Paper]. Technical Meeting on Low-Power Critical Facilities and Small Reactors, Ottawa, Canada. Unavailable
Marleau, G., Kennedy, G. G., & Chilian, C. (2010, November). Training new operators for the SLOWPOKE reactor at École Polytechnique : Theory and practice [Paper]. Technical Meeting on Low-Power Critical Facilities and Small Reactors, Ottawa, Canada. Unavailable
Martin, N., Marleau, G., & Hébert, A. (2023, November). A preliminary study of the OECD/NEA 3D transport problem using the lattice code DRAGON [Paper]. Symposium on Simulation Methods in Nuclear Engineering, Ottawa, Canada. Unavailable
Marleau, G. (2004, April). CANDU adjuster rods incremental cross sections evaluation: a perturbative approach [Paper]. PHYSOR 2004 - The physics of fuel cycles and advanced nuclear systems: global developments, Chicago, illinois, USA. Unavailable
Marleau, G. (2003, January). Approximate discontinuity factor evaluations in DRAGON [Paper]. 24th annual canadian nuclear society conference, Toronto. Unavailable
Marleau, G., & Varin, É. (2003, January). Transport analyses of 2-D CANDU diffusion calculations [Paper]. American nuclear society topical meeting in mathematics and computations, Gatlinburg, Tennessee, USA. Unavailable
Marleau, G., & Varin, É. (2002, January). Coolant void reactivity in a CANDU: a 2-D transport/diffusion comparison [Paper]. 22nd canadian nuclear society simulation symposium, Ottawa. Unavailable
Marleau, G., & Foissac, F. (2002, January). DRAGON analysis of MOX fueled VVER cell benchmarks [Paper]. 23rd annual canadian nuclear society conference, Toronto. Unavailable
Marleau, G., Hébert, A., & Roy, R. (2002). DRAGON programmer's manual. (Technical Report). Unavailable
Marleau, G. (2002, January). Verification of DRAGON: progress and lessons learned [Paper]. 23rd annual canadian nuclear society conference, Toronto. Unavailable
Marleau, G. (1999, September). Coherent anisotropic scattering homogenization in the B1 leakage model [Paper]. M&C 1999 mathematics and computation, reactor physics and environmental analysis in nuclear applications, Madrid, Spain. Unavailable
Marleau, G. (1996, October). Fine mesh 3-D collision probability calculations using the lattice code DRAGON [Paper]. International Conference on the Physics of Nuclear Science and Technology, Long Island, NY. Unavailable
Marleau, G., & Debos, E. (1998, October). Homogenization of linearly anisotropic scattering cross sections in a consistent B₁ heterogeneous leakage model [Paper]. 19th Annual Conference of the Canadian Nuclear Society, Toronto, Ontario (Canada). Unavailable
Marleau, G. (1998, October). New geometric capabilities of DRAGON [Paper]. 19th Annual Conference of the Canadian Nuclear Society, Toronto, Ontario (Canada). Unavailable
Marleau, G., Sissaoui, M. T., & Rousseau, K. Simulation of Vanadium detectors in DRAGON [Paper]. 19th Annual Conference of the Canadian Nuclear Society. Unavailable
Marleau, G., Noceir, S., Roy, R., & Rozon, D. (1997, June). Dragon modelling of the SLOWPOKE-2 reactor at École Polytechnique [Paper]. 1997 Canadian Nuclear Society Conference, Toronto, Can. Unavailable
Marleau, G., & Grammont, X. (1997, June). Fewgroup burnup calculations using time dependent microscopic cross sections [Paper]. 1997 Canadian Nuclear Society Conference, Toronto, Can. Unavailable
Marleau, G. A validation of DRAGON based on lattice experiments [Paper]. 5th International Conference on Simulation Methods in Nuclear Engineering, Montréal, Québec. Unavailable
Marleau, G., & Milgram, M. S. (1995, June). A DRAGON-MCNP comparison of axial diffusion subcoefficients [Paper]. 1995 Annual Meeting of American Nuclear Society, Philadelphia, PA. Published in Transactions of the American Nuclear Society, 72. Unavailable
Marleau, G., & Milgram, M. S. (1995, June). Dragon-MCNP comparison of void reactivity calculations [Paper]. 1995 16th Annual Conference of the Canadian Nuclear Society, Saskatoon, Can. Unavailable
Marleau, G., Roy, R., & Hébert, A. (1994, June). Finite element solution to the transport equation [Paper]. 15th Annual Conference of the Canadian Nuclear Society (CSN 1994), Montréal, Québec. Unavailable
Marleau, G. (1994). Response to "Comment on 'Analysis of cluster geometries using the DP1 approximation of the J₊ₒᵣ₋ technique" [Discussion or Letter]. Nuclear Science and Engineering, 116(3), 225-225. External link
Marleau, G., Roy, R., & Arsenault, B. (1994, October). Simulation of reactivity control devices in a CANDU-6 reactor using DRAGON [Paper]. 1994 nuclear simulation symposium, Pembroke (Canada). Unavailable
Naceur, A., & Marleau, G. (2019). CANDU-6 operation simulations using accident tolerant cladding candidates. Annals of Nuclear Energy, 124, 472-489. Available
Naceur, A., & Marleau, G. (2017). Neutronic analysis for accident tolerant cladding candidates in CANDU-6 reactors. Annals of Nuclear Energy, 113, 147-161. Available
Nuttin, A., Guillemin, P., Courau, T., Marleau, G., Méplan, O., David, S., Michel-Sendis, F., & Wilson, J. N. (2006, September). Study of CANDU Thorium-based Fuel Cycles with Monte Carlo and Deterministic Methods [Paper]. PHYSOR-2006, Vancouver, Canada. Unavailable
Paradis, M., Doligez, X., Marleau, G., Ernoult, M., & Thiollière, N. (2021, June). DONJON5/CLASS coupled simulations of MOX/UO2 heterogeneous PWR core [Paper]. 2021 Technical Workshop on Nuclear Fuel Cycle Simulation (TWoFCS 2021) (14 pages). Published in EPJ Nuclear Sciences & Technologies, 8. External link
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. External link
Prabha, H., Marleau, G., & Hébert, A. (2014). Tracking algorithms for multi-hexagonal assemblies (2D and 3D). Annals of Nuclear Energy, 69, 175-182. External link
Prabha, H., & Marleau, G. (2013). Computation of 3D neutron fluxes in one pin hexagonal cell. Annals of Nuclear Energy, 56, 1-6. External link
Prabha, H., & Marleau, G. (2012, April). Computation of neutron fluxes in clusters of fuel pins arranged in hexagonal assemblies (2D and 3D) [Paper]. International Conference on the Physics of Reactors 2012: Advances in Reactor Physics, PHYSOR 2012, Knoxville, TN, United states. Unavailable
Popov, A. V., Fehri, M. F., Chambon, R. P., Marleau, G., Teyssedou, A., Olekhnovitch, A., Popescu, O. M., & Mureithi, N. W. (2009, May). Ensuring negative coolant-void reactivity in CANDU Generation III+ [Paper]. International Conference on Mathematics, Computational Methods and Reactor Physics, Saratoga Springs, NY, United states. Unavailable
Popov, A. V., Assawaroongruengchot, M., Marleau, G., Hébert, A., & Karthikeyan, R. (2009, May). Validating models for coolant void reactivity evaluation in CANDU Generation III+ [Paper]. International Conference on Mathematics, Computational Methods and Reactor Physics 2009, Saratoga Springs, NY, United states. Unavailable
Popov, A. V., Chambon, R. P., Le Tellier, R., Marleau, G., & Hébert, A. (2023, September). Models for coolant void reactivity evaluation in CANDU Generation II and III+ [Paper]. International Conference on the Physics of Reactors, Interlaken, Switzerland. Unavailable
Popov, A. V., Marleau, G., & Olekhnovitch, A. (2008, October). The third generation of heavywater moderated reactors [Paper]. 16th Pacific Basin Nuclear Conference, Aomori, Japan. Unavailable
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. External link
Petrovic, I., Benoist, P., & Marleau, G. (1995, April). A simplified heterogeneous B₁ model with isotropically-reflected neutrons on assembly boundary [Paper]. International Conference on Mathematics and Computation, Reactor Physics, and Environmental Analyses, Portland, OR, USA. Unavailable
Petrovic, I., Benoist, P., & Marleau, G. (1994, October). A simplified heterogeneous B1 model with isotropically-reflected neutrons on assembly boundary [Paper]. 1994 nuclear simulation symposium, Pembroke (Canada). Unavailable
Qaddouri, A., Roy, R., Marleau, G., Goulard, B., & Mayrand, M. (1994, June). Multigroup flux solvers on parallel architecture [Paper]. 15th Annual Conference of the Canadian Nuclear Society, Montréal, Québec. Unavailable
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. External link
Raouafi, H., & Marleau, G. (2014, August). A simplified 3D DRAGON simulation of an inclined reactivity control device for the Canadian-SCWR [Paper]. 19th Pacific Basin Nuclear Conference (PBNC 2014), Vancouver, British Columbia, Canada. Unavailable
Raouafi, H., & Marleau, G. (2012, October). DRAGON 2-D simulation of spatial self-shielding effect in SLOWPOKE-2 reactor [Paper]. 24th Nuclear Simulation Symposium, Ottawa, Ontario, Canada. Unavailable
Raouafi, H., & Marleau, G. (2012, October). DRAGON and SERPENT 2-D modelling of the SLOWPOKE-2 reactor at École Polytechnique Montréal [Paper]. 24th Nuclear Simulation Symposium, Ottawa, Ontario, Canada. Unavailable
Roy, R., Marleau, G., & Hébert, A. (2010, May). Rudi Stamm'ler contributions and DRAGON [Paper]. International Conference on Advances in Reactor Physics to Power the Nuclear Renaissance (PHYSOR 2010), Pittsburgh, Pennsylvania. Unavailable
Roy, R., & Marleau, G. (2000, May). DRAGON solutions for benchmark BWR lattice cell problem [Paper]. PHYSOR 2000 american nuclear society international topical meeting, advances in reactor physics and mathematics and computation into the next millennium, Pittsburgh, PA, USA. External link
Roy, R., & Marleau, G. (2020, May). Dragon solutions for benchmark BWR lattice cell problems [Paper]. ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium (PHYSOR 2000), Pittsburgh, PA, USA. Unavailable
Roy, R., Hébert, A., & Marleau, G. (1996). Comments on "Investigation of Interface-Current Solution Techniques for Coupled Heterogeneous Cells" [Discussion or Letter]. Nuclear Science and Engineering, 122(2), 283-285. External link
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. External link
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. Available
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. External link
St-Aubin, E., & Marleau, G. (2015). CANDU-6 fuel optimization for advanced cycles. Nuclear Engineering and Design, 293, 371-384. Available
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. External link
St-Aubin, E., & Marleau, G. (2012, April). Modeling CANDU-6 liquid zone controllers for effects of thorium-based fuels [Paper]. International Conference on the Physics of Reactors 2012: Advances in Reactor Physics, PHYSOR 2012, Knoxville, TN, United states. Unavailable
St-Aubin, E., & Marleau, G. (2011, September). CANDU-6 devices reactivity worth adjustment for advanced fuel cycles [Paper]. 2nd International Conference on Physics and Technology of Reactors and Applications, Fez, Morocco. Unavailable
St-Aubin, E., & Marleau, G. (2011, June). An optimization scheme for selecting alternative fuels in CANDU-6 reactor [Paper]. 32nd Annual Conference of the CNS, Niagara Falls, Canada. Unavailable
Sarsour, H., Turinsky, P., Rahnema, F., Mosher, S., Serghiuta, D., Marleau, G., & Courau, T. (2002, January). Best estimate HELIOS/DRAGON/NESTLE codes simulation of a LOCA power pulse for a simplified CANDU-6 core [Paper]. 22nd canadian nuclear society simulation symposium, Ottawa. Unavailable
Sarsour, H., Rahnema, F., Mosher, S., Turinsky, P., Serghiuta, D., Marleau, G., & Courau, T. (2002, January). HELIOS//DRAGON//NESTLE codes simulation of void reactivity in a CANDU core [Paper]. 22nd canadian nuclear society simulation symposium, Ottawa. Unavailable
Sarsour, H., Turinsky, P., Rahnema, F., Mosher, S., Serghiuta, D., Marleau, G., & Courau, T. (2002, January). HELIOS/DRAGON/NESTLE codes Simulation of the Gentilly-3 loss of class 4 power event [Paper]. 22nd canadian nuclear society simulation symposium, Ottawa. Unavailable
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. External link
Shen, W., Rozon, D., & Marleau, G. Parametric analysis of Doppler coefficient of reactivity in DUPIC fuel by DRAGON [Paper]. 19th Annual Conference of the Canadian Nuclear Society. Unavailable
Sissaoui, M. T., Marleau, G., & Koclas, J. Xenon transients simulation using the reactor code DONJON [Paper]. 19th Annual Conference of the Canadian Nuclear Society. Unavailable
Sissaoui, M. T., Marleau, G., & Rozon, D. Accounting for actinide burnup history in CANDU reactor simulations [Paper]. Advances in nuclear fuel management II : topical meeting. Unavailable
Sissaoui, M. T., & Marleau, G. (1995, October). Application of the feedback model for the history base using DRAGON [Paper]. 19. CNS simulation symposium, Hamilton (Canada). Unavailable
Trancart, I., Marleau, G., & Doligez, X. (2024, October). Full core SSR-W simulations using DONJON5 [Paper]. 5th Genration IV and Small Reactors Conference (G4SR 2024), Ottawa, ON, Canada (13 pages). Unavailable
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. External link
Varin, E., & Marleau, G. (2006). CANDU reactor core simulations using fully coupled DRAGON and DONJON calculations. Annals of Nuclear Energy, 33(8), 682-691. External link
Varin, É., & Marleau, G. (2023, June). Validating the history-bases method in DRAGON/DONJON using G2 core follow-up [Paper]. CNS 2005 Annuel Conference, Toronto. Unavailable
Varin, É., & Marleau, G. (2004, January). First attempt at a CANDU-6 core tracking using the coupled DRAGON/DONJON calculations [Paper]. 6th international conference on simulation methods in nuclear engineering, Montréal, Québec. Unavailable
Varin, É., Marleau, G., & Chambon, R. (2003, January). Transport-diffusion coupling for CANDU reactor core follow-up [Paper]. International conference on supercomputing in nuclear applications SNA'2003, Paris, France. External link
Varin, É., Marleau, G., & Roy, R. (1994, October). Towards the generation of a consistent reactor cross-section database for CANDU-6 using DRAGON [Paper]. 1994 nuclear simulation symposium, Pembroke (Canada). Unavailable
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. External link
