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Dufour, P., Marleau, G., & Koclas, J. (juin 2004). Computation of surface fluxes in the lattice code DRAGON [Communication écrite]. 25th annual CNS conference - Nuclear energy: meeting the challenges, Toronto, Ontario, Canada. Non disponible
Dufour, P., Koclas, J., & Marleau, G. (janvier 2003). Reactor power computation using a model with three pseudo-fission products [Communication écrite]. 24th annual canadian nuclear society conference, Toronto. Non disponible
Dahmani, M., Wu, G. J., Roy, R., & Koclas, J. (octobre 2002). Development and parallelization of the three-dimensional characteristics solver MCI of dragon [Communication écrite]. International Conference on the New Frontiers of Nuclear Technology : Reactor Physics, Safety and High-Performance Computing (PHYSOR 2002), Seoul, Korea, Republic of. Non disponible
Dionne, B., Koclas, J., & Teyssedou, A. (janvier 2002). Study of coupling effects in steady-state CANDU core for different operating conditions [Communication écrite]. 23rd annual CNS conference, Toronto, Ontario, Canada. Non disponible
Dionne, B., Koclas, J., & Teyssedou, A. (janvier 2001). Parallel coupling of thermal-hydraulics and reactor physics for applications in a CANDU-6 [Communication écrite]. 22th annual conf. of the CNS, Toronto, Ontario. Non disponible
Kaveh, S., Koclas, J., & Roy, R. (mai 2000). Space-time kinetics calculations using coarse-grid acceleration technique [Communication écrite]. ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium (PHYSOR 2000), Pittsburgh, USA. Non disponible
Kaveh, S., Koclas, J., & Roy, R. (mai 1999). Improved quasi-static method vs. the direct method: a case study for CANDU reactor transients [Communication écrite]. Communicating the nuclear advantage. 39th Annual Canadian Nuclear Association Conference & 20th Annual Canadian Nuclear Society Conference, Montréal, Québec. Non disponible
Kaveh, S., Koclas, J., & Roy, R. (mai 1999). Simulation of CANDU reactor transients using hierarchical super nodal analysis [Communication écrite]. Communicating the nuclear advantage. 39th Annual Canadian Nuclear Association Conference & 20th Annual Canadian Nuclear Society Conference, Montréal, Québec. Non disponible
Koclas, J. (1998). Comparisons of the Different Approximations Leading to Mesh Centered Finite Differences Starting From the Analytic Nodal Method. Annals of Nuclear Energy, 25(11), 821-838. Lien externe
Kaveh, S., Koclas, J., Roy, R., & Buss, D. B. (octobre 1998). Three level space-time kinetics based on super nodal analysis [Communication écrite]. 19th annual conference of the Canadian Nuclear Society, Toronto, Ontario (Canada). Non disponible
Koclas, J., Sissaoui, M. T., & Marleau, G. (1997). Comparison between the multi-group improved and generalized quasistatic methods for different numbers of energy groups. Annals of Nuclear Energy, 24(15), 1223-1232. Lien externe
Koclas, J., Sissaoui, M. T., & Hébert, A. (1996). Solution of the improved and generalized quasi-static methods using an analytic calculation or a semiimplicit scheme to compute the precursor equations. Annals of Nuclear Energy, 23(11), 901-907. Lien externe
Mahjoub, M., & Koclas, J. (mai 2015). Comparative static simulations of a CANDU6 cell using different transport codes [Communication écrite]. 35th Annual Conference of the Canadian Nuclear Society and 38th CNS/CNA Student Conference 2015, Saint John, NB, Canada. Non disponible
Mahjoub, M., Roy, R., & Koclas, J. (2013). Generalized Perturbation Theory and Stochastics Algorithms Applied to Improve Candu6 Reflectors. Annals of Nuclear Energy, 53, 213-220. Lien externe
Mahjoub, M., Roy, R., & Koclas, J. (septembre 2011). Generalized perturbation therory estimates to improve CANDU6 reflectors [Communication écrite]. 2nd International Conference on Physics and Technology of Reactors and Applications, Fez Morocco. Non disponible
Sissaoui, M. T., Marleau, G., & Koclas, J. Xenon transients simulation using the reactor code DONJON [Communication écrite]. 19th Annual Conference of the Canadian Nuclear Society. Non disponible
Sissaoui, M. T., Koclas, J., & Herbert, A. (juin 1995). Solution of the improved and generalized quasi-static methods by Kaps-Rentrop integration with step-size control [Communication écrite]. 1995 Annual Meeting of American Nuclear Society, Philadelphia, PA. Publié dans Transactions of the American Nuclear Society, 72. Non disponible
Sissaoui, M. T., Koclas, J., & Hébert, A. (1995). Solution of the improved and generalized quasistatic methods by Kaps and Rentrop integration scheme with step size control. Annals of Nuclear Energy, 22(12), 763-774. Lien externe
Talebi, F., Marleau, G., & Koclas, J. (2006). A Model for Coolant Void Reactivity Evaluation in Assemblies of CANDU Cells. Annals of Nuclear Energy, 33(11-12), 975-983. Lien externe
Varin, É., Koclas, J., & Roy, R. (octobre 1995). Application of the DONJON reactor code for regulating system simulations [Communication écrite]. 19. CNS simulation symposium, Hamilton (Canada). Non disponible
Varin, É., Koclas, J., & Roy, R. (octobre 1995). Modeling of the CANDU-6 reactor regulating system [Communication écrite]. 1995 Winter Meeting of American Nuclear Society, San Francisco, CA. Publié dans Transactions of the American Nuclear Society, 73. Non disponible
