يعرض 1 - 20 نتائج من 39 نتيجة بحث عن '"Olekhnovitch, Andrei"', وقت الاستعلام: 0.46s تنقيح النتائج
  1. 1
    Conference
  2. 2
    Academic Journal

    Relation: Popov, A. V., & Olekhnovitch, A. (2012). Adapting the feed-back model to dynamic core heterogeneity. Annals of Nuclear Energy, 48, 134-137.

  3. 3
    Academic Journal

    Relation: Popov, A. V., Olekhnovitch, A., & Fehri, M. F. (2012). LBLOCA in CANDU-NG cooled by light water. Annals of Nuclear Energy, 45, 161-165.

  4. 4
    Academic Journal

    Relation: 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.

  5. 5
    Academic Journal

    Relation: 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.

  6. 6
    Academic Journal

    Relation: 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.

  7. 7
    Academic Journal

    Relation: 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.

  8. 8
    Academic Journal

    Relation: 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.

  9. 9
    Academic Journal

    المؤلفون: Olekhnovitch, Andrei

    Relation: Olekhnovitch, A. (2008). Wall Temperature Drop Observed Just Before Dryout Type Critical Heat Flux. International Journal of Thermal Sciences, 47(9), 1158-1168.

  10. 10
    Academic Journal

    Relation: 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.

  11. 11
    Academic Journal

    Relation: 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.

  12. 12
    Academic Journal

    Relation: 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.

  13. 13
    Academic Journal

    المؤلفون: Olekhnovitch, Andrei

    Relation: 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.

  14. 14
    Academic Journal

    Relation: 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.

  15. 15
    Academic Journal

    Relation: 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.

  16. 16
    Academic Journal

    Relation: 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.

  17. 17
    Academic Journal

    Relation: 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.

  18. 18
    Academic Journal

    Relation: 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.

  19. 19
    Academic Journal

    Relation: 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.

  20. 20
    Academic Journal

    Relation: 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.