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Documents dont l'auteur est "Tye, P."

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Nombre de documents: 28

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Bellil, A., Teyssedou, A., Bonnet, L., & Tye, P. (janvier 1999). Void drift in two interconnected subchannels [Communication écrite]. NURETH-9, San Francicso. Non disponible

Bonnet, L., Bellil, A., Tye, P., & Teyssedou, A. (1998). Implantation d'un nouveau modèle de migration latérale du taux de vide dans le code ASSERT-PV. (Rapport technique n° 239). Non disponible

Bédard, S., Teyssedou, A., Tye, P., & Midvidy, W. I. (septembre 1996). Effect of the position of an orifice with respect to an elbow in CCF [Communication écrite]. 5th International Conference on Simulation Methods in Nuclear Science and Engineering, Montréal, QC. Non disponible

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Kennedy, G. G., Tye, P., & St-Pierre, J. (2001). Loss-Free Counting With a Digital Spectrometer and a Software Program. Journal of Radioanalytical and Nuclear Chemistry, 248(2), 339-343. Lien externe

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Matuszkiewicz, A., Teyssedou, A., & Tye, P. (1996). Review of heat transfer correlations for the ASSERT thermal-hydraulics code. (Rapport technique n° 212). Non disponible

Matuszkiewicz, A., Teyssedou, A., & Tye, P. (1995). Review of drift flux correlations for the ASSERT thermal-hydraulics code. (Rapport technique n° 204). Non disponible

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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., & 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

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., & 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

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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

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Teyssedou, A., Önder, E. N., & Tye, P. (2005). Air-water counter-current slug flow data in vertical-to-horizontal pipes containing orifice type obstructions. International Journal of Multiphase Flow, 31(7), 771-792. Lien externe

Tye, P., Teyssedou, A., & Hernu, P. (2000). Comparison of ASSERT predictions using different void drift models against equilibrium void distribution experiments. (Rapport technique n° 221-R1). Non disponible

Teyssedou, A., & Tye, P. (1999). A Capacitive Two-Phase Flow Slug Detection System. Review of Scientific Instruments, 70(10), 3942-3948. Lien externe

Tye, P., Teyssedou, A., Tapucu, A., & Midvidy, W. I. (mai 1999). Prediction of the flooding point in a vertical to horizontal tube with and without obstructions [Communication écrite]. Communicating the nuclear advantage. 39th Annual Canadian Nuclear Association Conference & 20th Annual Canadian Nuclear Society Conference, Montréal, Québec. Non disponible

Tye, P., Teyssedou, A., & Hernu, H. (1997). Adiabatic counter-current flow in channels containing singularities. (Rapport technique n° 225, COG 97-329). Non disponible

Tye, P., Teyssedou, A., Troche, N., & Kiteley, J. (janvier 1996). Numerical study of the influence of the void drift model on the predictions of the ASSERT subchannel code [Communication écrite]. 5th International Conference on Simulation Methods in Nuclear Engineering, Montréal, Québec. Non disponible

Tye, P., Teyssedou, A., Tapucu, A., & Matuszkiewicz, A. (1995). Adiabatic two-phase flows in channels containing singularities - FY - 94. (Rapport technique n° 181). Non disponible

Tye, P., Teyssedou, A., & Bédard, S. (1995). Adiabatic two-phase flows in channels containing singularities- activities for FY-95. (Rapport technique n° 213). Non disponible

Tye, P., Matuszkiewicz, A., Teyssedou, A., Tapucu, A., & Midvidy, W. I. (janvier 1995). Counter-current flow in a vertical to horizontal tube with obstructions [Communication écrite]. 7th int. meeting nucl. reactor thermal-hydraulics NURETH-7, Saratoga. Lien externe

Tye, P., Teyssedou, A., & Troche, N. (1995). Review of void quality relationships: applicability to ASSERT. (Rapport technique n° 202). Non disponible

Tapucu, A., Teyssedou, A., Tye, P., & Troche, N. (1994). Effect of turbulent mixing models on the predictions of subchannel codes. Nuclear Engineering and Design, 149(1-3), 221-231. Lien externe

Tye, P., Matuszkiewicz, A., Teyssedou, A., Tapucu, A., Davidson, M., Midvidy, W., & Huynh, H. (juin 1994). Influence of flow obstructions on counter-current flow and flooding in vertical and horizontal tubes [Communication écrite]. 15th Annual Conference of the Canadian Nuclear Society, Montréal, Québec. Lien externe

Tye, P., Teyssedou, A., & Tapucu, A. (1994). Investigation of the constitutive relations for intersubchannel transfer mechanisms in horizontal flows as applied in the ASSERT-4 subchannel code. Nuclear Engineering and Design, 149(1-3), 207-220. Lien externe

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