Recommended set of interfacial drag correlations for the two-phase flow under thermal–hydraulic conditions of a horizontal steam generator

Investigation of the equalization capability of submerged perforated sheets under thermal–hydraulic conditions of a horizontal steam generator

(2020) T.T. Le et al.   ANNALS OF NUCLEAR ENERGY

Validation of the STEG code using PGV experiments on hydrodynamics of horizontal steam generator

(2019) Tung Thanh Le et al.   NUCLEAR ENGINEERING AND DESIGN

System thermalhydraulics for design basis accident analysis and simulation: Status of tools and methods and direction for future R&D

(2017) D. Bestion   NUCLEAR ENGINEERING AND DESIGN

Two-Phase Flow Field Simulation of Horizontal Steam Generators

(2017) Ataollah Rabiee et al.   Nuclear Engineering and Technology

Horizontal steam generator thermal hydraulic simulation in typical steady and transient conditions

(2016) Ataollah Rabiee et al.   NUCLEAR ENGINEERING AND DESIGN

A correlation for interfacial area concentration in high void fraction flows in large diameter channels

(2015) J.P. Schlegel et al.   CHEMICAL ENGINEERING SCIENCE

Drift flux modeling of the VVER-1000 horizontal nuclear steam generator

(2014) V. Ghazanfari et al.   PROGRESS IN NUCLEAR ENERGY

Study of perforated plate effect in horizontal WWER1000 steam generator

(2013) A. Safavi et al.   NUCLEAR ENGINEERING AND DESIGN

Two-group drift-flux model for closure of the modified two-fluid model

(2012) Caleb S. Brooks et al.   INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW

Interfacial area concentration in gas–liquid bubbly to churn-turbulent flow regime

(2012) B. Ozar et al.   INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW

Simulation of the Thermal Hydraulic Processes in the Horizontal Steam Generator with the Use of the Different Interfacial Friction Correlations

(2011) Vladimir Melikhov et al.   Science and Technology of Nuclear Installations

Void fraction and flow regime in adiabatic upward two-phase flow in large diameter vertical pipes

(2009) J.P. Schlegel et al.   NUCLEAR ENGINEERING AND DESIGN

Semi 2D modeling of the horizontal steam generator PGV-1000 using the RELAP5 code

(2009) E. Zarifi et al.   PROGRESS IN NUCLEAR ENERGY