Shah Nusrat Jahan Shanta,
Noor-Al-Din,
Abdus Sattar Mollah,
- Student, Department of Nuclear Science and Engineering Military Institute of Science and Technology, Mirpur Cantonment, Dhaka, India
- Student, Department of Nuclear, Science and Engineering Military Institute of Science and Technology, Mirpur Cantonment,, Dhaka, Bangladesh
- Professor, Department of Nuclear, Science and Engineering Military Institute of Science and Technology, Mirpur Cantonment,, Dhaka, India
Abstract
VVER-1200 is a Russian design reactor which consist of Two circuits comprising reactor core, piping, vertical steam generator, pressurizer, active and passive safety systems, turbine and generator. This reactor involves single phase flow from reactor core to steam generator (SG) where high pressurized water exchanges heat with normal water resulting in steam production. The flow is turbulent, which enables maximum efficiency to heat transfer. Using ANSYS Workbench’s multi-physics simulation capabilities, a typical computational model of a VVER-1200 grade shell-and-tube steam generator and its thorough thermal analysis are presented in this study. Temperature distribution curves are created using MATLAB to improve thermal behavior visualization and validation. The findings of the thermal study offer a thorough understanding of the steam generator’s temperature profile, axial and radial temperature distributions, and maximum and minimum heat flux values. The results assist safe operation and effective reactor performance by advancing knowledge of the thermal performance and heat transfer properties of the VVER-1200 steam generator. The heat SG is of shell and tube type. This research demonstrates a typical model of VVER 1200 grade shell and tube type steam generator along with thermal analysis Using Multi-physics Software ANSYS workbench. MATLAB is used to plot temperature distribution curve The thermal analysis depicts the temperature profile, axial and radial temperature distribution, as well as maximum and minimum heat flux of Steam Generator of VVER 1200 reactor.
Keywords: VVER-1200, ANSYS, Steam Generator, Heat Transfer, Thermal Analysis
[This article belongs to Journal of Thermal Engineering and Applications ]
Shah Nusrat Jahan Shanta, Noor-Al-Din, Abdus Sattar Mollah. Multiphysics Simulation and Thermal Characterization of VVER-1200 Steam Generator for Optimized Heat Transfer and Structural Integrity. Journal of Thermal Engineering and Applications. 2026; 13(01):7-15.
Shah Nusrat Jahan Shanta, Noor-Al-Din, Abdus Sattar Mollah. Multiphysics Simulation and Thermal Characterization of VVER-1200 Steam Generator for Optimized Heat Transfer and Structural Integrity. Journal of Thermal Engineering and Applications. 2026; 13(01):7-15. Available from: https://journals.stmjournals.com/jotea/article=2026/view=238886
References
- Sun Y. Unraveling the phenotypic features and functional mechanisms of tumor-associated adaptive natural killer cells (Doctoral dissertation, Karolinska Institutet).
- Rabie MA, Elshahat A, Hassan MH. Investigation of VVER-1200 pressurizer dynamics by adopting modelica based modeling. Progress in Nuclear Energy. 2022 Jan 1;143:104045.
- Sungur N, Paramonova IL. CALCULATION OF RELIABILITY ON JUSTIFICATION COOLING OF THE VVER-1200 CORE DURING THE OPERATION OF PASSIVE HEAT REMOVAL SYSTEM THROUGH STEAM GENERATOR. InProceedings of CONV-22: Int. Symp. on Convective Heat and Mass Transfer June 5–10, 2022, Turkey 2022. Begel House Inc..
- Blinkov VN, Dedov AV, Elkin IV, Melikhov VI, Melikhov OI, Nikonov SM, Nikulin AS. Horizontal Steam Generators: Design Improvement and Experimental-and-Computational Studies. Thermal Engineering. 2025 Apr;72(4):265-88.
- Roman MR, Ionescu VD, Olteanu G, Prisecaru I. Evaluation of radial temperature distribution in mixed oxide fuels. In2019 International Conference on ENERGY and ENVIRONMENT (CIEM) 2019 Oct 17 (pp. 109-112). IEEE.
- Hassan M, Riznic J. Evaluation of the integrity of steam generator tubes subjected to flow induced vibrations. Journal of Pressure Vessel Technology. 2014 Oct 1;136(5):051301.
- El-Morshedy SE, Awad MM, El-Fetouh MA. Thermal-Hydraulic modelling and analysis of VVER-1200 reactor core. Annals of Nuclear Energy. 2023 Dec 15;194:110125.
- Kandil A, El-Kady AA, El-Kafrawy A. Transient thermal stress analysis of thick-walled cylinders. International journal of mechanical sciences. 1995 Jul 1;37(7):721-32.
- Dwiddar MS, Badawi AA, Abou-Gabal HH, El-Osery IA. From VVER-1000 to VVER-1200: investigation of the effect of the changes in core. Inthe third international conference on physics and technology of reactors and applications, Tetuan, Morocco 2014 May 12.
- Roshchin MB, Sapiro VB, Markov SI. Effect of austenitization conditions on the plasticity of 10GN2MFA steel in repeated heating. Metal Science and Heat Treatment. 1982 Sep;24(9):607-12.
- Roshchin MB, Sapiro VB, Markov SI. Effect of austenitization conditions on the plasticity of 10GN2MFA steel in repeated heating. Metal Science and Heat Treatment. 1982 Sep;24(9):607-12.
- Jonšta P, Vlčková I, Krišták L, Špička I, Jonšta Z. Contribution to the thermal properties of selected steels. Metalurgija. 2015 Jan 1;54(1):187-90. https://www.tlv.com/steam-info/steam-theory/steam-basics/overall-heat-transfer-coefficient
- Егоров МЮ. Вертикальные парогенераторы для АЭС с ВВЭР. Известия высших учебных заведений. Ядерная энергетика. 2018(3):88-99.
- Shanta SN, Mollah AS. Structural and Thermal Analysis of Fuel Rod of VVER-1200 Nuclear Reactor Using ANSYS Software. MIST INTERNATIONAL JOURNAL OF SCIENCE AND TECHNOLOGY. 2025 Jun 30;13:65-71.
- Rabie MA, Elshahat AE, Hassan MH. Control oriented modeling of VVER-1200 using Modelica. Nuclear Engineering and Design. 2024 Apr 15;420:112980.
- Bhowmik PK, Schlegel JP. Multicomponent gas mixture parametric CFD study of condensation heat transfer in small modular reactor system safety. Experimental and Computational Multiphase Flow. 2023 Mar;5(1):15-28.

Journal of Thermal Engineering and Applications
| Volume | 13 |
| Issue | 01 |
| Received | 02/02/2026 |
| Accepted | 04/02/2026 |
| Published | 19/03/2026 |
| Publication Time | 45 Days |
Login
PlumX Metrics