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Boubcher, M., Marleau, G., & Rozon, D. (mai 1999). Development of an isotopic depletion method for reactor core calculations [Communication écrite]. Communicating the nuclear advantage. 39th Annual Canadian Nuclear Association Conference & 20th Annual Canadian Nuclear Society Conference, Montréal, Québec. Non disponible
Boubcher, M., Marleau, G., & Rozon, D. (octobre 1998). Pseudo-isotopes generation for the ²³⁵U and ²³⁸U depletion chains [Communication écrite]. 19th Annual Conference of the Canadian Nuclear Society, Toronto, Ontario (Canada). Non disponible
Chambon, R., Varin, E., & Rozon, D. (2007). Candu Fuel Management Optimization Using Alternative Gradient Methods. Annals of Nuclear Energy, 34(12), 1002-1013. Lien externe
Chambon, R., Varin, É., & Rozon, D. (juin 2023). CANDU fuel management optimization using generalized perturbation theory in the donjon diffusion code [Communication écrite]. CNS 2005 Annuel Conference, Toronto. Non disponible
Marleau, G., Noceir, S., Roy, R., & Rozon, D. (juin 1997). Dragon modelling of the SLOWPOKE-2 reactor at École Polytechnique [Communication écrite]. 1997 Canadian Nuclear Society Conference, Toronto, Can. Non disponible
Noceir, S., El Hajjaji, O., Varin, É., Roy, R., & Rozon, D. (juin 1997). Diffusion calculations for the SLOWPOKE-2 reactor using DONJON [Communication écrite]. 1997 Canadian Nuclear Society Conference, Toronto, Can. Non disponible
Rozon, D., & Shen, W. (2001). A Parametric Study of the Dupic Fuel Cycle to Reflect Pressurized Water Reactor Fuel Management Strategy. Nuclear Science and Engineering, 138(1), 1-25. Lien externe
Rozon, D., & Shen, W. (octobre 1998). Comparison of slightly enriched uranium fuel and MOX fuel in CANDU-6 reactor [Communication écrite]. Canadian Nuclear Society 19th annual conference, Toronto, Ontario (Canada). Publié dans Annual Conference Proceedings. Canadian Nuclear Society, 19(2). Non disponible
Rozon, D., Varin, É., Roy, R., & Brissette, D. Generalized perturbation theory estimates of zone level response to refueling perturbations in a CANDU 600 reactor [Communication écrite]. Advances in nuclear fuel management II : topical meeting. Non disponible
Rozon, D., & Kaveh, S. (juin 1997). SLOWKIN: A simplified model for the simulation of reactor transients in SLOWPOKE-2 [Communication écrite]. 1997 Canadian Nuclear Society Conference, Toronto, Can. Non disponible
Rozon, D., Roy, R., & Varin, É. (juin 1995). DRAGON/OPTEX predictions of channel power peaking factors and average exit burnup in CANDU-6 [Communication écrite]. 1995 Annual Meeting of American Nuclear Society, Philadelphia, PA. Publié dans Transactions of the American Nuclear Society, 72. Non disponible
Roy, R., Marleau, G., Tajmouati, J., & Rozon, D. (1994). Modelling of CANDU reactivity control devices with the lattice code DRAGON. Annals of Nuclear Energy, 21(2), 115-132. Lien externe
Sissaoui, M. T., Marleau, G., & Rozon, D. (1999). CANDU Reactor Simulations Using the Feedback Model With Actinide Burnup History. Nuclear Technology, 125(2), 197-212. Lien externe
Shen, W., & Rozon, D. (mai 1999). Effect of PWRA fuel management strategy on DUPIC fuel cycle [Communication écrite]. Communicating the nuclear advantage. 39th Annual Canadian Nuclear Association Conference & 20th Annual Canadian Nuclear Society Conference, Montréal, Québec. Non disponible
Shen, W., & Rozon, D. (octobre 1998). Generation of consistent nuclear properties of DUPIC fuel by DRAGON with ENDF/B-VI nuclear data library [Communication écrite]. Canadian Nuclear Society 19th annual conference, Toronto, Ontario (Canada). Publié dans Annual Conference Proceedings. Canadian Nuclear Society, 19(2). Lien externe
Shen, W., Rozon, D., & Marleau, G. Parametric analysis of Doppler coefficient of reactivity in DUPIC fuel by DRAGON [Communication écrite]. 19th Annual Conference of the Canadian Nuclear Society. Non disponible
Shen, W., & Rozon, D. (octobre 1998). Study of DUPIC fuel cycle in CANDU 6 reactor by DRAGON/DONJON [Communication écrite]. International Conference on the Physics of Nuclear Science and Technology, Long Island, NY. Non disponible
Sissaoui, M. T., Marleau, G., & Rozon, D. Accounting for actinide burnup history in CANDU reactor simulations [Communication écrite]. Advances in nuclear fuel management II : topical meeting. Non disponible
