Русская версия English version

Investigation into the processes of mixing of non-isothermal flows on a model of the ship nuclear power plant

A.A. Sataev, A.V. Duntsev

Vestnik IGEU, 2018 issue 5, pp. 26—32

Download PDF

Abstract in English: 

Background. To date, studying of mixing processes of water coolant flows is an urgent problem of the nuclear power industry. Leading scientific groups are investigating these processes at the experimental facilities ROCOM (Germany), Vattenfall (USA), Fortum PTS (Finland), OKB GIDROPRESS (Russia). The interest in these studies is associated with the appearance of new calculation codes that allow modeling these processes but they need to be verified. That is why it is an urgent problem to study the mixing processes on a model (single loop) of the reactor installation, as well as to investigate the effect of external dynamic forces on these processes.

Materials and methods. A one-loop experimental model has been proposed for the study of mixing processes. The model is a simulation of one closed loop of a nuclear power plant. The main difference from the known models consists in the measurement method, which is based on direct temperature probing of the mixing region and the possibility to carry out the research in dynamic regimes, whose analogs are not available in open data sources.

Results. We have constructed temperature distribution curves along the mixing region for nonisothermal flows with a gradient of 10, 20, 30, 40 оC for static and dynamic regimes and determined the areas of location of turbulent vortices and stagnant zones. It has been found that for the dynamic regime, when periodic oscillations with the amplitude of 30о are applied to the model, the steady-state regime onset time increases. We have determined the correlation between the temperature pulsations and periodic oscillations.

Conclusions. The single-loop model for studying the processes of mixing of non-isothermal flows has allowed us to estimate the inhomogeneities and stagnant regions occurring when a flow of imitation passes through the output block both in the static and dynamic regimes. The large amount of experimental data that has been accumulated can be used to verify CFD programs, to find ways to intensify these processes in the problems of design and construction of modern ship reactor installations.

References in English: 
  1. Dmitriev, S.M., Zverev, D.L., Bykh, O.A., Panov, Yu.K., Sorokin, N.M., Farafonov, V.A. Osnovnoe oborudovanie AES s korpusnymi reaktorami na teplovykh neytronakh [The main equipment of nuclear power plants with thermal neutron shell-type reactors]. Moscow: Mashinostroenie, 2013.
  2. Belova, O.V., Volkov, V.Yu., Skibin, A.P., Nikolaeva, A.V., Krutikov, A.A., Chernyshev, A.V.  Metodologicheskie osnovy CFD-raschetov dlya podderzhki proektirovaniya pnevmogidravlicheskikh sistem [Methodological foundations of CFD calculations for supporting of the design of pneumohydraulic systems]. Engineering Journal: Science and Innovation, 2013, no. 5. Available at: http: //engjournal.ru/catalog/machin/vacuum/763.html
  3. Barinov, A.A., Borodina, V.E., Dmitriev, S.M., Ignatov, E.D., Tabekin, A.A., Khrobostov, A.E. Vnedrenie metoda matrichnoy konduktometrii v issledovanie gidrodinamicheskikh protsessov techeniya teplonositelya v oborudovanii YaEU [Implementation of the matrix conductometry method in the study of hydrodynamic processes of coolant flow in nuclear power plant equipment]. Trudy Nizhegorodskogo gosudarstvennogo tekhnicheskogo universiteta
    im. R.E. Alekseeva
    [Collected works of Nizhny Novgorod State Technical University named after R.E. Alekseev], 2015, no. 1, pp. 139–145.
  4. Lisenkov, E.A., Bezrukov, Yu.A., Ul'yanovskiy, V.N., Saliy, L.A., Ul'yanovskiy, D.V., Zaytsev, D.V., Sergeev, S.G., Bykov, M.A., Zaytsev, S.I. Issledovanie peremeshivaniya teplonositelya v opusknoy kamere reaktora [A study of coolant mixing in the reactor downcomer]. Voprosy atomnoy nauki i tekhniki. Seriya Obespechenie bezopasnosti AES, 2008, no. 23, pp. 3–17.
  5. Hоhne, T., Kliem, S. Coolant mixing studies of natural circulation flows at the ROCOM test facility using ANSYS ANSYS-CFX. CFD4NRS, Garching, Germany, Proceedings, 2006, p. 23.
  6. Khlopkin, N.S. Morskaya atomnaya energetika [Marine nuclear power industry]. Moscow: MIFI, 2007.
  7. Sataev, A.A., Duntsev, A.V. Modelirovanie protsessov smesheniya neizotermicheskikh potokov oborudovaniya yadernykh energeticheskikh ustanovok [Modeling of mixing processes of non-isothermal flows of nuclear power plant equipment]. Sbornik dokladov XIII Mezhdunarodnoy nauchno-tekhnicheskoy konferentsii studentov, aspirantov i molodykh uchenykh «Energiya 2018» [Collected works of the13th international scientific and technical conference of students, graduate students and young scientists «Energy 2018»]. Ivanovo, 2018.
  8. Bol'shukhin, M.A., Budnikov, A.V., Fomichev, V.I., Sveshnikov, D.N., Romanov, R.I. Aktual'nye voprosy razvitiya eksperimental'noy bazy dannykh dlya verifikatsii CFD programm pri ikh ispol'zovanii v atomnoy energetike [Pressing issues of experimental database development for verifying CFD codes used in nuclear power industry]. Trudy Nizhegorodskogo gosudarstvennogo tekhnicheskogo universiteta im. R.E. Alekseeva [Collected works of Nizhny Novgorod State Technical University named after R.E. Alekseev], 2013, no. 2(99), pp. 117–125.
Key words in Russian: 
смешение неизотермических потоков, внешние динамические силы, температурное зондирование, судовая ядерная энергетическая установка, турбулентные вихри, застойные зоны, циркуляционная петля
Key words in English: 
mixing of nonisothermal flows, external dynamic forces, temperature probing, ship nuclear powerreactor installation, turbulent vortices, stagnant regions, loop
The DOI index: 
10.17588/2072-2672.2018.5.026-032
Downloads count: 
22