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An exact exit condition for multiphase critical flowLELLOUCHE, G. S.Nuclear engineering and design. 2001, Vol 205, Num 3, pp 251-263, issn 0029-5493Article

Two-phase critical flowELIAS, E; LELLOUCHE, G. S.International journal of multiphase flow. 1994, Vol 20, pp 91-168, issn 0301-9322, SUPArticle

Re: The boiling transition: analysis and data comparisons , by G. S. Lellouche, Nucl. Engrg. Des. 116, No. 2 (1989) 117-133. ResponseTONG, L. S; LELLOUCHE, G. S.Nuclear engineering and design. 1990, Vol 123, Num 1, pp 91-94, issn 0029-5493Article

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Quantifying reactor safety margins. I, an overview of the code scaling, applicability, and uncertainty evaluation methodologyBOYACK, B. E; CATTON, I; ZUBER, N et al.Nuclear engineering and design. 1990, Vol 119, Num 1, pp 1-15, issn 0029-5493Article

Quantifying reactor safety margins. IV, Uncertainty evaluation of LBLOCA analysis based on TRAC-PF1/MOD 1LELLOUCHE, G. S; LEVY, S; WULFF, W et al.Nuclear engineering and design. 1990, Vol 119, Num 1, pp 67-95, issn 0029-5493Article

Quantifying reactor safety margins. V, evaluation of scale-up capabilities of best estimate codesZUBER, N; WILSON, G. E; WULFF, W et al.Nuclear engineering and design. 1990, Vol 119, Num 1, pp 97-107, issn 0029-5493Article