Series: Nuclear and Reactor Constants

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

Authors & Affiliations

Melikhov O.I.1, Melikhov V.I.1, Nikonov S.M.1, Parfenov Y.V.2, Emelyanov D.A.2, Nerovnov A.A.2
1Electrogorsk Research and Engineering Center on NPP Safety, Electrogorsk, Russia
2Moscow Power Engineering Institute, Moscow, Russia

Parfenov Y.V. – Assoc. Prof., Head of the NPP Department of the MPEI, Dr.Sci. (Tech.), Moscow Power Engineering Institute. Contacts: 14, Krasnokazarmennya st., Moscow, Russia, 111250. Tel.: +7 (910) 476-02-78, e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it.
Melikhov O.I. – Senior Researcher, Deputy Director on the Scientific Work, Dr. Sci.(Phys.-Math.), Electrogorsk Research and Engineering Center on NPP Safety.
Melikhov V.I. – Senior Researcher, Head of the Computational Department, Dr. Sci.(Tech.), Electrogorsk Research and Engineering Center on NPP Safety.
Nikonov S.M. – Leading Researcher of the Experimental Department, Cand. Sci.(Tech.), Electrogorsk Research and Engineering Center on NPP Safety.
Emelyanov D.A. – Engineer, NPP Department of the MPEI, Moscow Power Engineering Institute.
Nerovnov A.A. – Engineer, NPP Department of the MPEI, Cand. Sci. (Tech.), Moscow Power Engineering Institute.


The results of the validation and improvement of the 3D thermalhydraulic STEG code developed in EREC and MPEI to model two-phase flows in the horizontal steam generator of the NPP with VVER are presented. The most difficult for the modeling thermalhydraulic processes occurred in the area of the submerged perforated sheet SPS was under investigation. The validation was performed on the basis of the experimental data obtained at the PGV test facility (EREC) which is the slice-model of the cross-section of the horizontal steam generator.

The two-fluid model of the two-phase flow is used in the STEG code. The preliminary calculations revealed the high sensibility to the interfacial friction correlations implemented in the code.

The possibility to change the interfacial friction coefficient in the required range of the void fraction in the required area of the numerical mesh was realized in the STEG code. The extensive calculation research was performed. It led to the significant improvement of the agreement between experimental and calculation results.

The modeling of the experiments at the PGV test facility carried out with the modified STEG code revealed that integral characteristics of the equalization are improved when SPS with uniform perforation is changed to the SPS with nonuniform perforation. However, the separation characterisitics are worse in the area with SPS with one perforation degree is attached to the SPS with another perforation degree.

two-fluid thermalhydraulic code, two-phase flow, mathematical model, horizontal steam generator, submerged perforated sheet, interfacial friction

Article Text (PDF, in Russian)


UDC 621.039.5

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2016, issue 2, 2:9