Void-fraction distribution under high-pressure boil-off conditions in rod bundle geometry

Proposed Correlation of Data for Isothermal Two-Phase, Two-Component Flow in Pipes

R.W. Lockhart · Chemical engineering progress · 1949 · 2.7K citations

Engineering, Heat Exchanger, Fluid Mechanics +12

The Thermal-Hydraulics of a Boiling Water Nuclear Reactor

P.A. Lottes · Nuclear Science and Engineering · 1978 · 210 citations

Core Thermal Hydraulics, Engineering, Physics +11

Full-range drift-flux correlation for vertical flows

B. Chexal, G.S. Lellouche · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1985 · 74 citations

Engineering, Fluid Mechanics, Gas-liquid Flow +16

Void fraction under high pressure, low flow conditions in rod bundle geometry

T.M. Anklam, R.F. Miller · Nuclear Engineering and Design · 1983 · 61 citations

Low Flow Conditions, Compressible Flow, Engineering +7

Experiments and void correlation for PWR small-break LOCA conditions

J.P. Cunningham, Hsu‐Chieh Yeh · Transactions of the American Nuclear Society · 1973 · 31 citations