Directory of Experts

Marleau, Guy

Directory of Experts

Marleau, Guy

Directory of Experts

Publications by type

Journal article (37) Conference paper (103) Book Book chapter Patent Report (2) Thesis Dataset Teaching resource Image Audio recording Video recording Other

Guy Marleau (142)

Journal articles (37)
- 2024
  - 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).
  - 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).
- 2022
  - Musongela, M., & Marleau, G. (2022). Generalization of the tibere B1 leakage model to the method of characteristics. Annals of Nuclear Energy, 174, 9 pages.
- 2019
  - Naceur, A., & Marleau, G. (2019). CANDU-6 operation simulations using accident tolerant cladding candidates. Annals of Nuclear Energy, 124, 472-489.
- 2018
  - 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.
  - 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.
- 2017
  - 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.
  - Naceur, A., & Marleau, G. (2017). Neutronic analysis for accident tolerant cladding candidates in CANDU-6 reactors. Annals of Nuclear Energy, 113, 147-161.
  - 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.
- 2016
  - 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.
  - 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.
  - 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.
- 2015
  - St-Aubin, E., & Marleau, G. (2015). CANDU-6 fuel optimization for advanced cycles. Nuclear Engineering and Design, 293, 371-384.
  - Dion, M., & Marleau, G. (2015). Eigenvalue implicit sensitivity to self-shielding calculations in heterogeneous geometries. Nuclear Science and Engineering, 179(2), 186-198.
  - 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.
- 2014
  - Prabha, H., Marleau, G., & Hébert, A. (2014). Tracking algorithms for multi-hexagonal assemblies (2D and 3D). Annals of Nuclear Energy, 69, 175-182.
- 2013
  - 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.
  - Prabha, H., & Marleau, G. (2013). Computation of 3D neutron fluxes in one pin hexagonal cell. Annals of Nuclear Energy, 56, 1-6.
  - 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.
- 2012
  - 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.
- 2011
  - Marleau, G., & Chambon, R. (2011). Fukushima, des notions techniques aux enseignements pratiques en passant par les conséquences. Physique au Canada, 67(4), 267-271.
- 2010
  - 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.
- 2008
  - 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.
  - 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.
  - 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.
- 2007
  - Assawaroongruengchot, M., & Marleau, G. (2007). Multigroup adjoint transport solution using the method of cyclic characteristics. Nuclear Science and Engineering, 155(1), 37-52.
  - Assawaroongruengchot, M., & Marleau, G. (2007). Perturbation Theory Based on the Method of Cyclic Characteristics. Nuclear Science and Engineering, 157(1), 30-50.
- 2006
  - 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.
  - Varin, E., & Marleau, G. (2006). CANDU reactor core simulations using fully coupled DRAGON and DONJON calculations. Annals of Nuclear Energy, 33(8), 682-691.
- 2003
  - Courau, T., & Marleau, G. (2003). Perturbation theory for lattice cell calculations. Nuclear Science and Engineering, 143(1), 19-32.
- 2002
  - Courau, T., & Marleau, G. (2002). Adjoint and Generalized Adjoint Flux Calculations Using the Collision Probability Technique. Nuclear Science and Engineering, 141(1), 46-54.
- 1999
  - 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.
- 1997
  - 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.
- 1996
  - 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.
  - 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.
- 1994
  - 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.
  - 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.
Conference papers (103)
- 2024
  - 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).
  - 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.
- 2023
  - 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.
  - 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.
  - 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.
  - 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.
- 2021
  - 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.
- 2020
  - 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.
- 2018
  - Marleau, G., & Hébert, A. (2018, October). DRAGON5 Workshop [Paper]. 8th International Conference on Simulation Methods in Nuclear Science and Engineering (8ICSMNSE), Ottawa, ON.
- 2017
  - 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).
  - 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).
- 2016
  - 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.
  - 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.
  - 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.
- 2015
  - Hébert, A., & Marleau, G. (2015, October). DRAGON5 Workshop [Paper]. 7th International Conference on Modelling and Simulation in Nuclear Science and Engineering (7ICMSNSE), Ottawa, Canada.
  - 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.
- 2014
  - 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.
  - 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.
  - 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.
- 2013
  - 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).
  - 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.
- 2012
  - Camand, C., & Marleau, G. (2012, October). Comparative study of DRAGON and TRIPOLI for a PWR assembly [Paper]. 24th Nuclear Simulation Symposium, Ottawa, Ontario, Canada.
  - 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.
  - 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.
  - 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.
  - 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.
  - 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.
  - 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.
  - 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.
  - Bejaoui, N., & Marleau, G. (2012, October). DRAGON simulation of a radial PWR reflector [Paper]. 24th Nuclear Simulation Symposium, Ottawa, Ontario, Canada.
  - 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.
  - 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.
- 2011
  - 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.
  - 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.
  - Harrisson, G., & Marleau, G. (2011, June). Modeling of a 3-D SCWR unit cell [Paper]. 32nd Annual Conference of the CNS, Niagara Falls, Canada.
  - 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.
  - 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.
- 2010
  - 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.
  - 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.
  - Altiparmakow, D., Shen, W., Marleau, G., & Rouben, B. (2010, May). Evolution of computer codes for CANDU analysis [Paper]. PHYSOR Topical Meeting, Pittsburgh, Pennsylvania.
  - 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.
  - 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.
  - 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.
  - Marleau, G., & Hébert, A. (2010, May). The GPT Saga at École Polytechnique [Paper]. 31st CNS Annual Conference, Montréal, Québec.
  - 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.
- 2009
  - 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.
  - 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.
  - 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.
  - 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.
  - 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.
  - 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.
  - 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.
- 2008
  - Popov, A. V., Marleau, G., & Olekhnovitch, A. (2008, October). The third generation of heavywater moderated reactors [Paper]. 16th Pacific Basin Nuclear Conference, Aomori, Japan.
- 2007
  - 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.
- 2006
  - 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.
  - Assawaroongruengchot, M., & Marleau, G. (2006, September). Generalized Perturbation Theory Based on the Method of Cyclic Characteristics [Paper]. PHYSOR-2006, Vancouver, Canada.
  - 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.
  - 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.
- 2005
  - 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.
  - 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.
- 2004
  - 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.
  - 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.
  - 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.
- 2003
  - Marleau, G. (2003, January). Approximate discontinuity factor evaluations in DRAGON [Paper]. 24th annual canadian nuclear society conference, Toronto.
  - 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.
  - 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.
  - 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.
- 2002
  - 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.
  - 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.
  - Marleau, G., & Foissac, F. (2002, January). DRAGON analysis of MOX fueled VVER cell benchmarks [Paper]. 23rd annual canadian nuclear society conference, Toronto.
  - 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.
  - 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.
  - Marleau, G. (2002, January). Verification of DRAGON: progress and lessons learned [Paper]. 23rd annual canadian nuclear society conference, Toronto.
- 2001
  - 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.
  - 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.
- 2000
  - 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.
  - 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.
- 1999
  - 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.
  - 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.
  - 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.
- 1998
  - 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).
  - Marleau, G. (1998, October). New geometric capabilities of DRAGON [Paper]. 19th Annual Conference of the Canadian Nuclear Society, Toronto, Ontario (Canada).
  - 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.
  - 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).
  - Marleau, G., Sissaoui, M. T., & Rousseau, K. Simulation of Vanadium detectors in DRAGON [Paper]. 19th Annual Conference of the Canadian Nuclear Society.
  - Sissaoui, M. T., Marleau, G., & Koclas, J. Xenon transients simulation using the reactor code DONJON [Paper]. 19th Annual Conference of the Canadian Nuclear Society.
- 1997
  - 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.
  - 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.
  - Marleau, G., & Grammont, X. (1997, June). Fewgroup burnup calculations using time dependent microscopic cross sections [Paper]. 1997 Canadian Nuclear Society Conference, Toronto, Can.
  - 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.
- 1996
  - Marleau, G. A validation of DRAGON based on lattice experiments [Paper]. 5th International Conference on Simulation Methods in Nuclear Engineering, Montréal, Québec.
  - 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.
- 1995
  - 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.
  - 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).
  - 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.
  - 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.
  - 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.
  - 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.
- 1994
  - 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).
  - 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.
  - 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.
  - 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).
  - 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).
Reports (2)
- 2002
  - Marleau, G., Hébert, A., & Roy, R. (2002). DRAGON programmer's manual. (Technical Report).
  - Courau, T., & Marleau, G. (2002). HELIOS based incremental cross sections generated using DRAGON. (Technical Report).

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Marleau, Guy

Directory of Experts

Marleau, Guy

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Guy Marleau (142)