EDN: XGYDCE
Authors & Affiliations
Didenko D.V.1, Baluev D.E.1, Nikanorov O.L.1, Rogozhkin S.A.1, Lubina A.S.2, Sedov A.A.2, Frolov A.A.2
1 Afrikantov Experimental Design Bureau for Mechanical Engineering, Nizhny Novgorod, Russia
2 National Research Center “Kurchatov Institute”, Moscow, Russia
Didenko D.V.1 – Design Engineer. Contacts: 15, Burnakovsky proezd, Nizhny Novgorod, Russia, 603074. Tel.: +7 (831) 246-94-03 (add. 44-13); e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Baluev D.E.1 – Lead Design Engineer.
Nikanorov O.L.1 – Head of Design Group, Cand. Sci. (Tech.).
Rogozhkin S.A.1 – Head of Department, Cand. Sci. (Tech.).
Lubina A.S.2 – Senior Researcher.
Sedov A.A.2 – Deputy Head of Department.
Frolov A.A.2 – Head of Laboratory, Cand. Sci. (Tech.).
Abstract
Cross-verification thermohydraulic calculations of the column of the core of the high-temperature gas-cooled reactor were performed according to four computers program: FlowVision, ANSYS CFX, ANSYS Fluent and ANSYS Mechanical APDL.
Design models have been developed in computer programs, including the main components of the core, such as graphite hexagonal prismatic fuel elements with fuel elements and channels for coolant passage, upper and lower reflectors, as well as an upper limiting device.
Modeling of coolant flow and heat exchange in the flow part of the column of fuel elements of the core was carried out within the framework of the turbulent flow gas model, taking into account the conjugate heat exchange with the graphite block and fuel elements.
The article presents the statement of the cross-verification task, a brief description of the core design and design models, features of the used programs for computers, as well as a comparison of the obtained calculation results, namely the temperatures of the core components and coolant heating, as well as the distribution of coolant flow rates and pressure drops along the height of the columns. Heat carrier heating irregularities in cooling channels and temperature irregularities in fuel elements are also compared.
Keywords
high temperature gas-cooled reactor, helium, reactor core, computational fluid dynamics, CFD, heat exchange, graphite, cross-verification, FlowVision, ANSYS
Article Text (PDF, in Russian)
References
- Energeticheskaya strategiya Rossiyskoy Federatsii na period do 2035 goda, utverzhdena rasporyazheniem Pravitel'stva Rossiyskoy Federatsii ot 9 iyunya 2020 g. № 1523-r. [Energy Strategy of the Russian Federation through 2035, approved by Russian Government Order No. 1523-r of June 9, 2020].
- Kontseptsiya razvitiya vodorodnoy energetiki v Rossiyskoy Federatsii, utverzhdena rasporyazheniem Pravitel'stva Rossiyskoy Federatsii ot 5 avgusta 2021 g. № 2162-r. [Concept for the Development of Hydrogen Energy in the Russian Federation, approved by Russian Government Order No. 2162-r of August 5, 2021].
- Fateev S.A., Petrunin V.V., Kodochigov G.N., Marov I.V., Alekseev S.V., Ipatov P.L., Petrov A.Yu., Ponomarev-Stepnoy N.N., Shutikov A.V. Development of Atomic-Hydrogen Energy Technologies in the Rosatom State Corporation. At Energy, 2023, vol. 133, issue 5–6, pp. 251–258. DOI: https://doi.org/10.1007/s10512-023-01004-4.
- Abrosimov N.G., Kodochigov N.G., Kuznetsov L.E., Petrunin V.V., Ponomarev-Stepnoi N.N., Sukharev Yu. P. HTGR – New Prospects for Nuclear Energy. At Energy, 2020, vol. 129, issue 1, pp. 43–45. DOI: https://doi.org/10.1007/s10512‑021‑00709‑8.
- Didenko D.V., Baluev D.E., Marov I.V., Nikanorov O.L., Rogozhkin S.A., Sorokin S.E. Raschetnoe modelirovanie teplophizicheskih processov v vysokotemperaturnom gazoohlazhdaemom reaktore [Computational modeling of the thermal and physical processes in the high-temperature gas-cooled reactor]. Komp’yuternye issledovaniya i modelirovanie – Computer Research and Modeling, 2023, vol. 15, no. 4, pp. 895–906. DOI: 10.20537/2076-7633-2023-15-4-895-906.
- Rukovodstvo pol'zovatelya programmnogo kompleksa FlowVision [FlowVision User Guide]. Available at: https://flowvision.ru/ru/support‑menu‑header‑ru/download‑ru/ (accessed 11.11.2025).
- CAE EXPERT. Integrator tekhnologiy ANSYS v Rossii i stranakh SNG [ANSYS technology integrator in Russia and the CIS]. Ansys CFX. Available at: https://cae-expert.ru/product/ansys-cfx (accessed 11.11.2025).
- CAE EXPERT. Integrator tekhnologiy ANSYS v Rossii i stranakh SNG [ANSYS technology integrator in Russia and the CIS]. Ansys Fluent. Available at: https://cae-expert.ru/product/ansys-fluent (accessed 11.11.2025).
- CAE EXPERT. Integrator tekhnologiy ANSYS v Rossii i stranakh SNG [ANSYS technology integrator in Russia and the CIS]. Available at: https://cae-expert.ru/ (accessed 11.11.2025).
- Programma dlya EVM FlowVision [Computer program FlowVision]. Attestation passport. Registration No. 591, 2023.
- Bedenig D. Gasgekühlte Hochtemperaturreaktoren [Gas cooled high temperature reactor]. München, Verlag Karl. Thiemig, 1972. 245 p.
- Kodochigov N.G. Yadernye energeticheskie ustanovki s vysokotemperaturnymi modul’nymi gazoohlazhdaemymi reaktorami [Nuclear power plants with high temperature modular gas-cooled reactors]. Nizhniy Novgorod: Nizhny Novgorod State Technical University n.a. R. E. Alekseev, 2017. 745 p.
- Patankar S. Numerical heat transfer and fluid flow. New York, Hemisphere Publishing Corporation, 1980. 214 p.
- Wilcox D.C. Turbulence modeling for CFD. DCW Industries, Inc., 1994. 460 p.
- Menter F.R. Two-Equation Eddy-Viscosity Turbulence Models for Engineering Applications. AIAA Journal, August 1994, vol. 32(8), p. 1598.
UDC 621.039.513:621.039.52.034.3
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2025, no. 4, 4:16
