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	Post-dryout heat transfer assessment of trace Aounallah, Y. (2017). Post-dryout heat transfer assessment of trace. In 37th annual conference of the canadian nuclear society and 41st annual cns/cna student conference. Canadian Nuclear Society. Detailed Record
	Simulations with TRACE of a BWR/4 steam line break under "hot standby" conditions Aounallah, Y. (2017). Simulations with TRACE of a BWR/4 steam line break under "hot standby" conditions. In Vol. 1. 37th annual conference of the canadian nuclear society & 41st CNS/CNA student conference 2017 (pp. 218-228). Canadian Nuclear Society. Detailed Record Published Version
	TRACE/S3K code coupling simulations of a BWR/4 anticipated transient without scram Aounallah, Y. (2017). TRACE/S3K code coupling simulations of a BWR/4 anticipated transient without scram. In Vol. 2. Proceedings of the 37th annual conference of the Canadian Nuclear Society & 41st CNS/CNA student conference 2017 (pp. 1000-1013). Canadian Nuclear Society (CNS). Detailed Record Published Version
	Simulations of level-swell experiments with TRACE Aounallah, Y. (2016). Simulations of level-swell experiments with TRACE (p. N11A0125 (13 pp.). Presented at the 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11). . Detailed Record Published Version
	Assessment of TRACE against single-tube post-dryout heat transfer experiments Aounallah, Y. (2014). Assessment of TRACE against single-tube post-dryout heat transfer experiments (p. 1192 (12 pp.). Presented at the 10th international topical meeting on nuclear thermal-hydraulics, operation and safety (NUTHOS-10). . Detailed Record Published Version
	Simulation of HALDEN IFA-650 loss-of-coolant accidents tests with TRACE Aounallah, Y. (2012). Simulation of HALDEN IFA-650 loss-of-coolant accidents tests with TRACE. Kerntechnik, 77(5), 316-323. https://doi.org/10.3139/124.110214 Detailed Record
	Development of a wide-range pre-CHF convective boiling correlation Aounallah, Y. (2010). Development of a wide-range pre-CHF convective boiling correlation. Journal of Nuclear Science and Technology, 47(4), 357-366. https://doi.org/10.3327/jnst.47.357 Detailed Record Published Version
	A separate-effect-based new appraisal of convective boiling and its suppression Aounallah, Y. (2008). A separate-effect-based new appraisal of convective boiling and its suppression. Journal of Nuclear Science and Technology, 45(2), 149-159. https://doi.org/10.3327/jnst.45.149 Detailed Record Published Version
	A separate-effect-based new appraisal of convective boiling and its suppression Aounallah, Y. (2008). A separate-effect-based new appraisal of convective boiling and its suppression. Journal of Nuclear Science and Technology, 45(2), 149-159. https://doi.org/10.1080/18811248.2008.9711424 Detailed Record Published Version
	Void fraction and critical power assessment of CORETRAN-01/VIPRE-02 Aounallah, Y. (2004). Void fraction and critical power assessment of CORETRAN-01/VIPRE-02. Nuclear Technology, 145(2), 163-176. https://doi.org/10.13182/NT04-A3467 Detailed Record Published Version
	VIPRE-02 subchannel validation against NUPEC BWR void fraction data Aounallah, Y., & Coddington, P. (1999). VIPRE-02 subchannel validation against NUPEC BWR void fraction data. Nuclear Technology, 128(2), 225-232. https://doi.org/10.13182/NT99-A3027 Detailed Record Published Version