Skip to main content
Log in

Simulation of the Coolant Hydrodynamics in the Outlet Section of the Fuel Assembly of the Cartridge Core of the RITM Type Reactor

  • NUCLEAR POWER PLANTS
  • Published:
Thermal Engineering Aims and scope Submit manuscript

Abstract

The results of experimental studies into the hydrodynamics of the coolant at the outlet section of the cassette fuel assembly (FA) of the RITM-type reactor of a low-power ground-based nuclear power plant are presented. The purpose of the work is to analyze the distribution of the axial velocity and flow rate of the coolant at the exit from the fuel bundle, in the modernized head of the fuel assembly, near the coolant extraction pipe and the openings of the upper base plate as well as to determine those areas of the fuel bundle from which the coolant flow is most likely to enter the pipe selection to the resistance thermometer. To achieve this goal, experiments were carried out on a research stand with an air working medium on a model of the outlet section of a fuel cassette, which includes an outlet fragment of a fuel bundle with spacer grids, models of an upgraded fuel cassette head, an upper support plate, and a coolant extraction pipe. When studying the flow of the coolant flow in the outlet part of the fuel cassette, the pneumometric method and the method of injection of a contrasting impurity were used. An area covering the entire cross section of the model was chosen as the area under study. The picture of the coolant flow is represented by cartograms of the distribution of its axial velocity and flow rate as well as cartograms of the distribution of the contrasting impurity in the cross section of the experimental model. The results of the experiments can serve as a basis for making engineering decisions when designing new cores of RITM type reactors. The obtained database of experimental data can be used for validation of modern CFD programs and one-dimensional thermal-hydraulic codes used to justify the thermal reliability of cores.

This is a preview of subscription content, log in via an institution to check access.

Access this article

Price excludes VAT (USA)
Tax calculation will be finalised during checkout.

Instant access to the full article PDF.

Fig. 1.
Fig. 2.
Fig. 3.
Fig. 4.
Fig. 5.
Fig. 6.
Fig. 7.
Fig. 8.
Fig. 9.
Fig. 10.
Fig. 11.
Fig. 12.

Similar content being viewed by others

REFERENCES

  1. D. L. Zverev, Yu. P. Fadeev, A. N. Pakhomov, V. Yu. Galitskikh, V. I. Polunichev, K. B. Veshnyakov, S. V. Kabin, and A. Yu. Turusov, “Reactor installations for nuclear icebreakers: Origination experience and current status,” At. Energy 129, 18–26 (2020).

    Article  Google Scholar 

  2. D. L. Zverev, O. B. Samoilov, O. A. Morozov, A. A. Zakharychev, V. Yu. Silaev, P. B. Matyash, A. Yu. Vishnev, M. M. Kashka, and O. E. Darbinyan, “Active zones of existing nuclear icebreakers,” Sudostroenie, No. 1(848), 13–16 (2020).

    Google Scholar 

  3. V. M. Belyaev, M. A. Bol’shukhin, A. N. Pakhomov, A. M. Khizbullin, A. N. Lepekhin, V. I. Polunichev, K. B. Veshnyakov, A. N. Sokolov, and A. Yu. Turusov, “The world’s first floating NPP: Origination and direction of future development,” At. Energy 129, 27–34 (2020).

    Article  Google Scholar 

  4. V. V. Petrunin, “Reactor units for small nuclear power plants,” Herald Russ. Acad. Sci. 91, 335–346 (2021). https://doi.org/10.1134/S1019331621030126

    Article  Google Scholar 

  5. A. A. Barinov, S. M. Dmitriev, A. E. Khrobostov, and O. B. Samoilov, “Methods of thermomechanical reliability validation of thermal water-moderated and water-cooled reactor cores,” At. Energy 120, 335–341 (2016).

    Article  Google Scholar 

  6. S. M. Dmitriev, A. V. Varentsov, A. A. Dobrov, D. V. Doronkov, A. N. Pronin, V. D. Sorokin, and A. E. Khrobostov, “Computational and experimental investigations of the coolant flow in the cassette fissile core of a KLT-40S reactor,” J. Eng. Phys. Thermophys. 90, 941–950 (2017).

    Article  Google Scholar 

  7. S. M. Dmitriev, A. A. Barinov, A. V. Varentsov, D. V. Doronkov, D. N. Solntsev, and A. E. Khrobostov, “Experimental studies of local coolant hydrodynamics using a scaled model of cassette-type fuel assembly of a KLT-40S reactor,” Therm. Eng. 63, 567–574 (2016). https://doi.org/10.1134/S0040601516080048

    Article  Google Scholar 

  8. A. A. Gukhman, Introduction to the Theory of Similarity, 2nd ed. (Vysshaya Shkola, Moscow, 1973) [in Russian].

    MATH  Google Scholar 

  9. S. M. Dmitriev, A. A. Dobrov, M. A. Legchanov, and A. E. Khrobostov, “Application of multihole pressure probe for research of coolant velocity profile in nuclear reactor fuel assemblies,” Prib. Metody Izmer. 6, 188–195 (2015).

    Google Scholar 

Download references

Funding

The work was carried out within the framework of the state task in the field of scientific activity (subject no. FSWE-2021-0008).

Author information

Authors and Affiliations

Authors

Corresponding author

Correspondence to D. V. Doronkov.

Rights and permissions

Reprints and permissions

About this article

Check for updates. Verify currency and authenticity via CrossMark

Cite this article

Dmitriev, S.M., Demkina, T.D., Dobrov, A.A. et al. Simulation of the Coolant Hydrodynamics in the Outlet Section of the Fuel Assembly of the Cartridge Core of the RITM Type Reactor. Therm. Eng. 70, 523–533 (2023). https://doi.org/10.1134/S0040601523070017

Download citation

  • Received:

  • Revised:

  • Accepted:

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1134/S0040601523070017

Keywords:

Navigation