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Concerning the location of void detachment in annuliLELLOUCHE, G. S.Nuclear engineering and design. 1994, Vol 151, Num 1, pp 259-264, issn 0029-5493Article

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A void fraction correlation for generalized applicationsCHEXAL, B; LELLOUCHE, G; HOROWITZ, J et al.Progress in nuclear energy (New series). 1992, Vol 27, Num 4, pp 255-295, issn 0149-1970Article

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Quantifying reactor safety margins. III, assessment and ranging of parametersWULFF, W; BOYACK, B. E; ZUBER, N et al.Nuclear engineering and design. 1990, Vol 119, Num 1, pp 33-65, issn 0029-5493Article

Quantifying reactor safety margins. VI, A physically based method of estimating PWR large break loss of coolant accident PCTCATTON, I; DUFFEY, R. B; WULFF, W et al.Nuclear engineering and design. 1990, Vol 119, Num 1, pp 109-117, issn 0029-5493Article

Quantifiying reactor safety margins; II, Characterization of important contributors to uncertaintyWILSON, G. E; BOYACK, B. E; ZUBER, N et al.Nuclear engineering and design. 1990, Vol 119, Num 1, pp 17-31, issn 0029-5493Article

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