FONESYS: The FOrum & NEtwork of SYStem Thermal-Hydraulic Codes in Nuclear Reactor Thermal-Hydraulics

The influence of interfacial pressure forces on the character of two-phase flow model equations

James H. Stuhmiller · International Journal of Multiphase Flow · 1977 · 267 citations

Engineering, Physics, Fluid Dynamics +11

8th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-8

Journal of Nuclear Science and Technology · 1997 · 195 citations

Engineering, Mechanical Engineering, Nuclear Engineering +14

The three-level scaling approach with application to the Purdue University Multi-Dimensional Integral Test Assembly (PUMA)

Mamoru Ishii, Shripad T. Revankar, Tauna Leonardi et al. · Nuclear Engineering and Design · 1998 · 127 citations

Engineering, Mechanical Engineering, Metrology +4

Thermal-Hydraulic System Codes in Nulcear Reactor Safety and Qualification Procedures

A. Petruzzi, Francesco Saverio D'Auria · Science and Technology of Nuclear Installations · 2008 · 116 citations · Full text

Engineering, Nuclear Engineering, Systems Engineering +16

The Best Estimate Plus Uncertainty (BEPU) approach in licensing of current nuclear reactors

F. D’Auria, C. Camargo, O. Mazzantini · Nuclear Engineering and Design · 2012 · 113 citations

Engineering, Nuclear Engineering, Nuclear Safety Analysis +13