Modeling thermophysical processes in a nuclear reactor on fast neutrons

Authors

  • I.E. Berezovskaya Al–Farabi Kazakh National University, Kazakhstan, Almaty
  • G.A. Vityuk Institute of Atomic Energy of the National Nuclear Center of the Republic of Kazakhstan, Kazakhstan, Kurchatov
  • K.O. Toleubekov Al–Farabi Kazakh National University, Kazakhstan, Almaty

DOI:

https://doi.org/10.26577/RCPh-2019-i3-8
        127 111

Keywords:

fast reactors, heat transfer, heat carrier, temperature

Abstract

The development of reactors on the fast neutrons and nuclear power engineering is generally responsible for its formation. One of them is that the responsibility for the reliability of the reactor equipment, its calculation, creation and operation sharply increases. For the development of projects in the field of nuclear energy, it is necessary to carry out various thermalhydraulic calculations. Using the results of calculations will allow for timely adjustment in the engineering. This work is devoted to the study of the processes of hydrodynamics and heat exchange of reactor on fast neutrons with an electrical power of 600 MW with a volumetric energy release up to 0.494 GW / m3. In the process of work, 3D model of the selected fuel assembly area was created in the program Gambit. Computer modeling was carried out in the ANSYS FLUENT software package as a result of which thermal state of fuel assembly for established mode of heat transfer was defined. The calculations were carried out using the k-ε coolant motion turbulent model. This article presents the results of calculations on hydrodynamics and heat transfer in a segment of the selected fuel assembly of a fast sodium reactor. The non-uniformity of temperature distributions along the height of the active zone in various areas of fuel assemblies, the distribution of the heat carrier velocity, as well as pressure indicators are shown. The analysis of the results obtained shows that the temperatures of the structural elements do not exceed the permissible temperatures; the pressure drop is significantly lower than in reactors of another type.

References

1 А.А. Akatov and Y. Koryakovskiy, Future of nuclear power. Reactors on fast neutrons, (Moscow, ANO "ICAO", 2012), p.7-8. (in Russ).

2 S.Z. Zhiznin and V.M. Timokhov, Journal of MGIMO University, 6 (45), 215-248 (2015). (in Russ.)

3 M.V. Frolov and O.V. Vishtak, Young Scientist journal, Kazan, 22.5 (102.5), 16-17 (2015). (in Russ)

4 A.A. Goverdovskiy, S.G. Kalyakin, and V.I. Rachkov, Thermal Engineering, 5, 3–10 (2014). (in Russ)

5 S.S. Gordeyev, A.P. Sorokin, B.B. Tikhomirov, A.A. Trufanov, and N.A. Denisova, Atomic energy, 122 (1), 17-25 (2017). (in Russ)

6 P.J. Erbacher, Nuclear Engineering and Design, 103 (1), 55-64 (1987).

7 B.B. Tikhomirov, V.M. Poplavskiy, Influence of statistical characteristics of the bundle of fuel assemblies on the evaluation of the temperature regime of the active zone of a fast sodium reactor (Proseedings of Universities. Nuclear Power Engineering, 2014, no. 2), p.128-139. (in Russ)

8 M.D. Carelli, C.W. Bach, Transactions of the American Nuclear Society, 21 (1), 393-395 (1975).

9 I. Kuznetsov and V. Poplavskiy, The safety of NPP with fast neutron reactor (Moscow: IzDat., 2012), p.631. (in Russ).

10 V. Kumaev, A. Lebezov, V. Alexeev Development and application of MASKA-LM code for calculation of thermal
hydraulics and mass transfer of lead cooled fast reactors (Proc. 11th Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-11). Avignon, France, 2005), p. 191/1-191/61.

11 A.P. Sorokin, A.A. Series: Nuclear reactor constants, 3, 142-162 (2018). (in Russ)

12 A.P. Sorokin, Kuzina A. Ju, A.I. Orlov, Series: Nuclear reactor constants, 3, 240-265 (2018). (in Russ).

13 A. Sorokin, Y. Kuzina and A. Orlov, Modeling of thermophysical processes in support new generation fast reactor projects with liquid metal heat carrier, Materialy konferencii, (Obninsk , 2018), p.11-13. (in Russ).

14 A.L. Sirotkina, I.I. Loschakov, Global Nuclear Safety, 1 (6), 67–77 (2013). (in Russ).

15 Yu.M. Semchenkov, Thermal engineering, 5, 2–9 (2011). (in Russ).

16 O. Baturin, N. Baturin and V. Matveev, Building computational models in the Gambit preprocessor of the universal software complex Fluent (Samara, 2010), p 166. (in Russ).

17 V. Levin, Nuclear physics and nuclear reactors (Moscow, Atomizdat, 1979), p 288. (in Russ).

18 P.Kirilov, Y.Yuriev and V.Bobkov, Handbook of Thermo-Hydraulic Calculations (Moscow, Energoatomizdat, 1990), p. 360. (in Russ).

19 A.Korotkikh and I.Shamanin, Thermalhydraulic processes in a nuclear reactor and the calculation of their basic parameters (Tomsk: TPU, 2008), p 108. (in Russ).

20 P. Kirilov and N. Deniskina, Thermophysical properties of liquid metal coolants (Мoscow, 2000), p 42. (in Russ).

21 V. Chirkin, Thermophysical properties of materials of nuclear engineering (Moscow: Atomizdat, 1968), p.356 (in Russ).

22 M. Ibragimov, V.Subbotin and P.Ushakov. Study of heat transfer in turbulent flow in pipes of liquid metals (Moscow, 1960), pp. 54–56. (in Russ).

23 ANSYS Fluent Tutorial Guide (Southpointe, 2013), p.1034.

24 N. Galin and P. Kirilov. Heat and mass transfer (in nuclear power) (Moscow, Energoatomizdat, 1987), p 376. (in Russ).

25 P. Ovchinnikov, L. Golubev, V. Dobrynin, V. Klochkov, V. Semenov, and V Tsybenko. Operating models of Pressurized water reactors (Мoscow: Atomizdat, 1977), p 280. (in Russ).

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How to Cite

Berezovskaya, I., Vityuk, G., & Toleubekov, K. (2019). Modeling thermophysical processes in a nuclear reactor on fast neutrons. Recent Contributions to Physics (Rec.Contr.Phys.), 70(3), 64–72. https://doi.org/10.26577/RCPh-2019-i3-8

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Section

Thermal Physics and Theoretical Thermal Engineering