G.S. Lellouche

Quantifying reactor safety margins part 1: An overview of the code scaling, applicability, and uncertainty evaluation methodology

B.E. Boyack, I. Catton, Romney B. Duffey et al. · Nuclear Engineering and Design · 1990 · 205 citations · Full text

Reliability, Safety Engineering, Safety-critical System +13

A void fraction correlation for generalized applications

B. Chexal, G.S. Lellouche, J. Horowitz et al. · Progress in Nuclear Energy · 1992 · 156 citations

Generalized Applications, Generalized Function, Validated Numerics +2

Two-phase critical flow

E. Elias, G.S. Lellouche · International Journal of Multiphase Flow · 1994 · 140 citations

Engineering, Physics, Phase Equilibrium +7

Mathematical Methods in Nuclear Reactor Dynamics

Ziya Akcasu, G.S. Lellouche, Louis Μ. Shotkin et al. · IEEE Transactions on Systems Man and Cybernetics · 1972 · 101 citations

Numerical Analysis, Nuclear Reactor Dynamics, Engineering +4

Quantifying reactor safety margins: Application of code scaling, applicability, and uncertainty evaluation methodology to a large-break, loss-of-coolant accident

B.E. Boyack, Romney B. Duffey, G.E. Wilson et al. · 1989 · 100 citations

Reliability, Safety Engineering, Safety-critical System +14