EDN: OWPAYH
Authors & Affiliations
Dmitriev S.M., Demkina T.D., Doronkov Dmitriev S.M., Demkina T.D., Doronkov D.V., Doronkova D.S., Dobrov A.A., Pronin A.N., Kuritsin D.D., Ryazanov A.V., Nikolaev D.S.
Nizhny Novgorod State Technical University n.a. R.E. Alekseev, Nizhny Novgorod, Russia
Dmitriev S.М. – Rector, Professor, Dr. Sci. (Tech.).
Demkina Т.D. – Junior Research Assistant. Contacts: 24, Minina st., Nizhny Novgorod, Nizhny Novgorod region, Russia, 603950. Tel.: +7 (831) 436-80-17; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Doronkov D.V. – Senior Researcher, Cand. Sci. (Tech.).
Doronkova D.S. – Graduate Student.
Dobrov А.А. – Senior Researcher.
Pronin А.N. – Research Assistant.
Kuritsin D.D. – Engineer.
Rayzanov А.V. – Research Assistant.
Nikolaev D.S. – Assistant.
Abstract
The article presents the results of an experimental study of coolant flow hydrodynamic features in the inlet section of the fuel assembly of the RITM-type reactor cassette core of a low-power nuclear power plant. The purpose of the work is to study the influence of different design elements of the inlet section on the redistribution of the axial velocity of the coolant flow. To achieve the goal, a series of experiments was carried out on a large-scale experimental model, including structural elements of the inlet section from the calibration washer to the fuel rod attachment unit to the diffuser, as well as the span of the fuel rod bundle between the absorber grid and the first spacer grid. The studies were carried out using the pneumometric method in several characteristic sections along the length of the model. The location of the measurement points covers the entire cross section of the model. Features of the coolant flow are visualized by cartograms of the axial flow velocity of the working medium, as well as graphs of the axial velocity along the cross section of the fuel rod bundle. The results of experimental modeling were used to optimize the hydraulic profiling of the structural elements of the fuel assembly inlet section. The resulting experimental data base can be used to validate the domestic CFD program LOGOS, as well as to refine the methods for thermohydraulic calculation of cores in a cell-by-cell approximation.
Keywords
core, fuel assembly, calibration washer, inlet section, fuel rod bundle, absorption grid, spacer grid, central displacer, coolant hydrodynamics, axial velocity, flow
Article Text (PDF, in Russian)
References
- Petrunin V.V., Sheshina N.V., Fateev S.A. et al. Scientific and technical aspects of developing a RITM-200N innovative reactor for SNPPs. At Energy, 2023, vol. 134, issue 1, pp. 1–10. DOI: https://doi.org/10.1007/s10512-023-01020-4.
- Belyaev V.M., Bol’shukhin M.A., Pakhomov A.N. et al. The World’s First Floating NPP: Origination and Direction of Future Development. At Energy, 2020, vol. 129, issue 1, pp. 27–34. DOI: https://doi.org/10.1007/s10512-021-00707-w.
- Samoilov O.B., Romanov A.I., Galitskikh V.Yu., Zakharychev A.A., Morozov O.A., Mitrofanov A.V., Silaev V.Yu. Analiz opyta ekspluatatsii aktivnykh zon atomnykh ledokolov pervogo pokoleniya. Baza dannykh v obosnovaniye i razvitiye novykh atomnykh ledokolov i plavuchikh energoblokov [Analysis of operating experience of first-generation nuclear icebreakers' cores. Database for substantiation and development of new nuclear icebreakers and floating power units]. Tekhnologii obespecheniya zhiznennogo tsikla yadernykh energeticheskikh ustanovok – Technologies for Ensuring the Life Cycle of Nuclear Power Plants, 2023, issue 3, pp. 16–24.
- Dmitriev S.M., Samoilov O.B., Kupriyanov A.V. et al. Experimental Investigations of the Onset and Growth of a Heat-Transfer Crisis in a Full-Scale Cross-Sectional Model FA of the RITM-200 Reactor for Small NPP. At Energy, 2022, vol. 133, issue 1, pp. 30–34. DOI: https://doi.org/10.1007/s10512-023-00968-7.
- Beliavskii S., Anikin N., Alhassan S., Kudeev S., Nesterov V. Effect of fuel nuclide composition on the fuel lifetime of the RITM-200 reactor unit. Annals of Nuclear Energy, 2022, vol. 173, pp. 1–9. DOI: https://doi.org/10.1016/j.anucene.2022.109105.
- Beliavskii S., Alhassan S., Danilenko V., Karvan R., Nesterov V. Effect of changing the outer fuel element diameter on thermophysical parameters of KLT-40S reactor unit. Annals of Nuclear Energy, 2023, vol. 190, pp. 1–8. DOI: https://doi.org/10.1016/j.anucene.2023.109877.
- Zhiqiang Wu, Jinsen Xie, Pengyu Chen, Yingjie Xiao, Zining Ni, Tao Liu, Nianbiao Deng, Aikou Sun, Tao Yu. Performance of different absorber materials and move-in/out strategies for the control rod in small rod-controlled pressurized water reactor: A study based on KLT-40 model. Nuclear Engineering and Technology, 2024, vol. 56, pp. 1–11. DOI: https://doi.org/10.1016/j.net.2024.02.037.
- Dmitriev S.M., Barinov A.A., Khrobostov A.E. et al. Methods of Thermomechanical Reliability Validation of Thermal Water-Moderated and Water-Cooled Reactor Cores. At Energy, 2016, vol. 120, issue 5, pp. 335–341. DOI: https://doi.org/10.1007/s10512-016-0140-9.
- Dmitriev S.M., Barinov A.A., Varentsov A.V. et al. Experimental studies of local coolant hydrodynamics using a scaled model of cassette-type fuel assembly of a KLT-40S reactor. Therm. Eng., 2016, vol. 63, issue 8, pp. 567–574. DOI: https://doi.org/10.1134/S0040601516080048.
- Dmitriev S.M., Dobrov A.A., Legchanov M.A., Khrobostov A.E. Application of multihole pressure probe for research of coolant velocity profile in nuclear reactor fuel assemblies. Devices and Methods of Measurement, 2015, vol. 6, no. 2, pp. 188–195.
- Gukhman A.A. Vvedeniye v teoriyu podobiya: uchebnoye posobiye dlya studentov vysshikh tekhniche-skikh uchebnykh zavedeniy [Introduction to the theory of similarity: a textbook for students of higher technical educational institutions]. Moscow, 2010. Available at: https://www.elibrary.ru/item.asp?id=19460780 (accessed 15.11.2024).
UDC 621.039
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2024, no. 4, 4:19
