EPRXDL
Authors & Affiliations
Dmitriev S.M., Demkina T.D., Dobrov A.A., Doronkov D.V., Doronkova D.S., Pronin A.N., Ryazanov A.V.
Nizhny Novgorod State Technical University n.a. R.E. Alekseev, Nizhny Novgorod, Russia
Doronkov D.V. – Senior Researcher, Cand. Sci. (Tech.). Contacts: 24, Minina st., Nizhny Novgorod, 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..
Dmitriev S.М. – Professor, Rector, Dr. Sci. (Tech.).
Demkina Т.D. – Junior Research Assistant.
Dobrov А.А. – Senior Researcher.
Doronkova D.S. – Graduate Student.
Pronin А.N. – Research Assistant.
Rayzanov А.V. – Research Assistant.
Abstract
The article presents the results of studying the peculiarities of coolant hydrodynamics at the outlet of heads of different designs of cassette-type fuel assembly in the core of a RITM-type reactor of a nuclear icebreaker and a low-power nuclear power plant. The experiments were carried out on a research stand with an air working medium on a model of the outlet section of a fuel cassette using the pneumometric method and the contrast impurity injection method, based on the theory of hydrodynamic similarity. The hydrodynamic picture of the coolant flow is visualized using axial velocity cartograms at the outlet of the fuel rod bundle, behind the heads of fuel assemblies of several types of design, in front of the extraction pipe and in the upper support plate. Determination of the areas of the fuel rod bundle from which the flow could enter the coolant extraction pipe was carried out by the method of supplying a contrast impurity. The research results made it possible to establish the influence of the design of the fuel assembly head on the inhomogeneity of the axial flow of the coolant flow at the outlet of the fuel bundle and in front of the upper support plate. The mixing of the coolant behind the head of the fuel assembly of a nuclear icebreaker reactor is more intense compared to the head of the fuel cassette of a low-power nuclear plant reactor, which is due to the heterogeneity of the flow when exiting the passage holes of the heads.
Keywords
core, fuel assembly, outlet section, extraction tube, head, support plate, spacer grid, fuel bundle, coolant, axial velocities, contrast agent, axial flow
Article Text (PDF, in Russian)
References
- Petrunin V.V., Sheshina N.V., Fateev S.A., Kurachenkov A.V., Shchekin D.V., Brykalov S.M., Bezrukov A.A. Scientific and technical aspects of developing a RITM-200N innovative reactor for SNPPs. At Energy, 2023, vol. 134, issue 1–2, pp. 1–10. DOI: https://doi.org/10.1007/s10512-023-01020-4.
- Petrunin V.V. Reaktornyye ustanovki dlya atomnykh stantsiy maloy moshchnosti [Reactor Units for Small Nuclear Power Plants]. Vestnik Rossiyskoy akademii nauk – Bulletin of the Russian Academy of Sciences, 2021, vol. 91, issue 3, pp. 335–346. DOI: 10.1134/S1019331621030126.
- Belyaev V.M., Bol'shukhin M.A., Pakhomov A.N., Khizbullin A.M., Lepekhin A.N., Polunichev V.I., Veshnyakov K.B., Sokolov A.N., Turusov A.Yu. The World's First Floating NPP: Origination and Direction of Future Development. At Energy, 2020, vol. 129, issue 1, pp. 3–13. DOI: 10.1007/s10512-021-00707-w.
- Filippov S.P., Veselov F.V., Pankrushina T.G. Prospects of SNPPs in the electric power in-dustry. At Energy, 2023, vol. 134, issue 1–2, pp. 11–20. DOI: 10.1007/s10512-023-01021-3.
- 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 icebreaker cores. Database in support of development of new nuclear icebreakers and floating nuclear 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.
- Zverev D.L., Fadeev Yu.P., Pakhomov A.N., Galitskikh V.Yu., Polunichev V.I., Veshnyakov K.B., Kabin S.V., Turusov A.Yu. Reactor installations for nuclear icebreakers: origination experience and current status. At Energy, 2020, vol. 129, issue 1, pp. 18–26. DOI: 10.1007/s10512-021-00706-x.
- Romanov A.I., Papotin V.Yu., Tuturkin M.Yu. Razrabotka aktivnykh zon dlya ASMM i PEB. Tekushcheye sostoyaniye i napravleniya razvitiya [Reactor core development for SNPP and FPU current status and development trends]. Voprosy atomnoy nauki i tekhniki. Seriya: Materialovedeniye i novyye materialy – Problems of Atomic Science and Technology. Series: Materials Science and New Materials, 2023, issue 5, pp. 86–111.
- Zverev D.L., Samoilov O.B., Morozov O.A., Zakharychev A.A., Silaev V.Yu., Matyash P.B., Vishnev A.Yu., Kashka M.M., Darbinyan O.E. Aktivnyye zony deystvuyushchikh atomnykh ledokolov [The cores of operating nuclear icebreakers]. Sudostroenie – Shipbuilding, 2020, issue 1, pp. 13–16.
- Kulakov G.V., Vatulin A.V., Ershov S.A., Konovalov Yu.V., Morozov A.V., Savchenko A.M., Sorokin V.I., Romanov A.I., Morozov O.A., Shishin V.Yu., Sheldyakov A.A. Razrabotka topliva dlya atomnykh stantsiy maloy moshchnosti i plavuchikh energoblokov, sostoyaniye i perspektivy [Development of fuel for low power reactors and floating power units. Status and prospects]. Voprosy atomnoy nauki i tekhniki. Seriya: Materialovedeniye i novyye materialy – Problems of Atomic Science and Technology. Series: Materials Science and New Materials, 2020, issue 1, pp. 116–128.
- Zakharychev A.A., Iksanova G.S., Kupriyanov A.V., Osin A.B., Petrunin V.V., Samoilov O.B., Shipov D.L. Methodological issues and results of experimental and computational studies of critical heat flows in RITM-200 reactor fuel assemblies for small NPP. At Energy, 2021, vol. 130, issue 2, pp. 63–68. DOI: 10.1007/s10512-021-00775-y.
- 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.
- Barinov A.A., Dmitriev S.M., 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. 35–41. DOI: https://doi.org/10.1007/s10512-016-0140-9.
- Dmitriev S.M., Gerasimov A.V., Dobrov A.A., Doronkov D.V., Pronin A.N., Ryazanov A.V., Solntsev D.N., Khrobostov A.E., Noskov A.S., Samoilov O.B., Shvetsov Yu.K., Shipov D.L. Eksperimental'noye issledovaniye techeniya potoka teplonositelya v aktivnoy zone reaktora VVER s TVSA [Experimental investigation of the coolant flow in the VVER reactor core with TVSA fuel assemblies]. Izvestiya vuzov. Yadernaya Energetika, 2020, issue 4, pp. 25–36. DOI: 10.26583/npe.2020.4.03.
- 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. Primeneniye mnogokanal'nogo pnevmometricheskogo zonda dlya issledovaniy profilya skorosti teplonositelya v modelyakh toplivnykh kasset yadernykh reaktorov [Application of multihole pressure probe for research of coolant velocity profile in nuclear reactor fuel assemblies]. Pribory i metody izmerenij – Devices and Methods of Measurement, 2015, vol. 6, no. 2, pp. 188–195.
UDC 621.039
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2025, no. 2, 2:16
