The results of the validation of the STEG code using the experiments on two-phase flow
across horizontal tube bundles are presented. The experiments are carried out on two water …

The results of a study on the equalization of a non-uniform steam load using submerged
perforated sheets (SPSs) are presented. The experimental data obtained at the PGV test …

A set of interfacial drag correlations is proposed for describing two-phase flows under
thermal–hydraulic conditions of a horizontal steam generator (SG). This set of correlations …

Nuclear steam generator is a critical component of the pressurized-water nuclear power
plant that plays an important role in security and efficiency of the nuclear power plant …

The analysis of steam generators as an interface between primary and secondary circuits in
light water nuclear power plants is crucial in terms of safety and design issues. VVER-1000 …

During the operation of nuclear power systems, the occurrence of leakage accidents of
primary and secondary condensers are a major concern due to the potential threat to safe …

The paper is devoted to the study of the features of the flow of a steam-water mixture in a
horizontal steam generator, which is one of the main components of nuclear power plants …

The STEG code is a three-dimensional two-fluid code designed for modeling thermal-
hydraulic processes. To study thermal-hydraulic processes in the horizontal steam generator …

Steam Generator (SG) is one of the main components of the power cycle in pressurized
water reactor (PWR), and it is the hub of primary coolant circuit and secondary circuit, so the …

The advantages of using natural circulation (NC) as a cooling system, has prompted the
worldwide development to investigate this phenomenon more than before. The interesting …