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Popov, A. V., & Olekhnovitch, A. (2012). Adapting the feed-back model to dynamic core heterogeneity. Annals of Nuclear Energy, 48, 134-137. Lien externe
Popov, A. V., Li, X., Olekhnovitch, A., & Fassi Fehri, M. (2012). Further improving LBLOCA resistance of CANDU cooled by light water. Annals of Nuclear Energy, 50, 256-262. Lien externe
Popov, A. V., Olekhnovitch, A., & Fehri, M. F. (2012). LBLOCA in CANDU-NG cooled by light water. Annals of Nuclear Energy, 45, 161-165. Lien externe
Popov, A. V., Fehri, M. F., Chambon, R. P., Marleau, G., Teyssedou, A., Olekhnovitch, A., Popescu, O. M., & Mureithi, N. W. (mai 2009). Ensuring negative coolant-void reactivity in CANDU Generation III+ [Communication écrite]. International Conference on Mathematics, Computational Methods and Reactor Physics, Saratoga Springs, NY, United states. Non disponible
Haoues, L., Olekhnovitch, A., & Teyssedou, A. (2009). Numerical study of the influence of the internal structure of a horizontal bubbly flow on the average void fraction. Nuclear Engineering and Design, 239(1), 147-157. Lien externe
Olekhnovitch, A., Sun, J., & Teyssedou, A. (2008). A Complex but Accurate Correlation for Predicting Critical Heat Flux in a Round Tube for Low and Medium Pressures Under Circumferentially Non-Uniform Heating Conditions. International Journal of Heat and Mass Transfer, 51(7-8), 2041-2054. Lien externe
Haoues, L., Olekhnovitch, A., & Teyssedou, A. (2008). Influence of the void fraction profile on the distribution parameter C0 for a bubbly gas-liquid flow in a horizontal round pipe. Nuclear Engineering and Design, 238(4), 1155-1158. Lien externe
Olekhnovitch, A., & Teyssedou, A. (octobre 2008). Method and apparatus for studying water choking flow under supercritical pressure conditions [Communication écrite]. International Workshop "Supercritical Water and Steam in Nuclear Power Engineering : Problems and Solutions, Moscow, Russia. Non disponible
Haoues, L., Olekhnovitch, A., & Teyssedou, A. (mai 2008). Numerical study of the influence of the internal structure of a horizontal bubbly flow on the average void fraction [Communication écrite]. 16th International Conference on Nuclear Engineering (ICONE 16), Orlando, Florida. Non disponible
Popov, A. V., Marleau, G., & Olekhnovitch, A. (octobre 2008). The third generation of heavywater moderated reactors [Communication écrite]. 16th Pacific Basin Nuclear Conference, Aomori, Japan. Non disponible
Olekhnovitch, A. (2008). Wall Temperature Drop Observed Just Before Dryout Type Critical Heat Flux. International Journal of Thermal Sciences, 47(9), 1158-1168. Lien externe
Olekhnovitch, A. (août 2007). Particularités du flux de chaleur critique à des pressions faibles [Communication écrite]. 18e Congrès français de mécanique, Grenoble, France. Non disponible
Olekhnovitch, A. (2007). Unusual characteristics of onset nucleate boiling and heat transfer crisis for forced convection flow of water in uniformly heated round tubes. Fiziko-tehnitcheskie problemy yadernoi energetiki, 8, 36-37. Non disponible
Sun, J., Olekhnovitch, A., Tye, P., & Teyssedou, A. (juin 2005). Critical heat flux (CHF) data in vertical flows subjected to angular non-uniform heat flux distributions [Communication écrite]. CNS Annual Conference, Toronto. Non disponible
Olekhnovitch, A., Teyssedou, A., Tye, P., & Felisari, R. (2005). An empirical correlation for calculating steam-water two-phase pressure drop in uniformly heated vertical round tubes. International Journal of Multiphase Flow, 31(3), 358-370. Lien externe
Olekhnovitch, A., & Teyssedou, A. (2004). Method of treatment of experimental data for heat transfer crisis in dispersed-annular steam-water flow. Fiziko-tehnitcheskie problemy yadernoi energetiki, MEPhI-2004, 8, 157-158. Non disponible
Olekhnovitch, A., Teyssedou, A., & Tye, P. (2002). On the Round Table Discussion on Reactor Power Margins Published in Nuclear Engineering and Design 163 (1-2). Nuclear Engineering and Design, 216(1-3), 239-245. Lien externe
Olekhnovitch, A., Teyssedou, A., Tye, P., & Champagne, P. (2001). Critical Heat Flux Under Choking Flow Conditions - Part I - Outlet Pressure Fluctuations. Nuclear Engineering and Design, 205(1-2), 159-173. Lien externe
Olekhnovitch, A., Teyssedou, A., & Tye, P. (2001). Critical Heat Flux Under Choking Flow Conditions - Part II - Maximum Values of Flow Parameters Attained Under Choking Flow Conditions. Nuclear Engineering and Design, 205(1-2), 175-190. Lien externe
Teyssedou, A., & Olekhnovitch, A. (2001). Experimental study of CHF in the horizontal convection bank and wall membrane tubes of industrial boilers. (Rapport technique n° P2622). Non disponible
Olekhnovitch, A., Teyssedou, A., & Tye, P. (2000). New Representation of the Dryout Type Critical Heat Flux. International Journal of Thermal Sciences, 39(1), 63-73. Lien externe
Olekhnovitch, A., Teyssedou, A., & Tye, P. (2000). On the Round Table Discussion on Reactor Power Margins Published in Nuclear Engineering and Design 163 (1-2) 1996. Nuclear Engineering and Design, 201(2-3), 335-346. Lien externe
Olekhnovitch, A., Teyssedou, A., Tapucu, A., Champagne, P., & Groeneveld, D. C. (1999). Critical heat flux in a vertical tube at low and medium pressures. Pt. I. Experimental results. Nuclear Engineering and Design, 193(1-2), 73-89. Lien externe
Olekhnovitch, A., Teyssedou, A., & Tye, P. (1999). Critical heat flux in a vertical tube at low and medium pressures. Pt. II. New data representation. Nuclear Engineering and Design, 193(1-2), 91-103. Lien externe
Olekhnovitch, A., Teyssedou, A., & Tye, P. (janvier 1999). Nouvelle représentation du flux de chaleur critique [Communication écrite]. IVe colloque interunversitaire Franco-Québécois, Montréal, Québec. Non disponible
Olekhnovitch, A. (1997). Etude du flux de chaleur critique à des pressions faibles [Thèse de doctorat, École Polytechnique de Montréal]. Disponible
Teyssedou, A., Olekhnovitch, A., Tapucu, A., Champagne, P., & Groeneveld, D. (1994). Critical heat flux data in a vertical tube at low and medium pressures. Nuclear Engineering and Design, 149(1-3), 185-194. Lien externe
