IMPROVEMENT OF METHODS FOR MODELING THE MELTING OF FUEL ASSEMBLIES IN THE CONDITIONS OF AN EXPERIMENT ON IGR RECTOR
https://doi.org/10.52676/1729-7885-2025-2-151-164
Abstract
Experimental studies of the process of fuel destruction at the IGRY reactor make it possible to obtain data on the processes occurring in the fuel assemblies of various types of nuclear reactors during severe accidents. One of the stages of severe accidents is the melting of nuclear fuel. One of the stages of severe accidents is the melting of nuclear fuel. In this paper, we consider the complex application of physical models of the ANSYS FLUENT software module to achieve explicit dynamic melting of elements of a fuel assembly. Computational studies are carried out on a two-dimensional model of an experimental reactor device. The calculation models «volume of fluid» and «solidification melting» are used, which allow modeling the movements of the liquid fraction of the elements of the fuel assembly. To set the energy release, a user defined function (UDF) of the Fluent module is used.
About the Authors
E. A. KabdylkakovKazakhstan
Kurchatov
A. S. Suraev
Kazakhstan
Kurchatov
O. M. Zhanbolatov
Kazakhstan
Kurchatov
G. A. Vityuk
Kazakhstan
Kurchatov
R. A. Irkimbekov
Kazakhstan
Kurchatov
References
1. https://www.gen-4.org/generation-iv-criteria-andtechnologies/sodium-fast-reactor-sfr
2. Batyrbekov E. et al. Experimental opportunities and main results of the impulse graphite reactor use for research in safety area // Annals of Nuclear Energy. – 2023. – Vol. 182. – P. 109582.
3. Zhanbolatov О.М., Irkimbekov R.A., Mukhamedov N.E. Calculation of the power diagram of an experimental device with a neutron converter // NNC RK Bulletin. – 2020. – No. 4. – P. 82–87. (In Russ.) https://doi.org/10.52676/1729-7885-2020-4-82-87
4. Suleimenov N.A., Pakhnits A.V., Suraev A.S. In-reactor experiment for the testing of a fast-reactor pile in the conditions of loss-of-coolant accident // NNC RK Bulletin. – 2019. – No. 1. – P. 133–138. (In Russ.) https://doi.org/10.52676/1729-7885-2019-1-133-138
5. Kotov V.М., Zhanbolatov О.M., Suleymenov N.A. Substantiation of an experimental study technology of fuel rods of fast reactors in the IGR // NNC RK Bulletin. – 2020. – No. 1. – P. 62–67. (In Russ.) https://doi.org/10.52676/1729-7885-2020-1-62-67
6. Mukhamedov N.Ye., Vityuk V.A., Vityuk G.A., Vurim A.D., Kelsingazina R.Ye., Dolzhikov S.A., Zhengis D.T., Suraev A.S. Computational studies in support of possibility of conducting an in-pile experiment with power reactor fuel during the implementation of the long-term operation mode of the IGR reactor // NNC RK Bulletin. – 2024. – No. 4. – P. 88–95. (In Russ.) https://doi.org/10.52676/1729-7885-2024-4-88-95
7. Skakov M.K., Mukhamedov N.Ye., Pakhnits A.V., Deryavko I.I. Nuclear reactor corium properties obtained at IGR research reactor // NNC RK Bulletin. – 2019. – No. 1. – P. 129–132. (In Russ.) https://doi.org/10.52676/1729-7885-2019-1-129-132
8. Batyrbekov E.G., Skakov M.K., Vityuk V.A., Baklanov V.V., Vurim A.D., Pakhnits A.V., Kamiyama K., Matsuba K. Experimental studies in substantiation of sodium cooled fast reactors safety // NNC RK Bulletin. – 2018. – No. 3. – P. 117–121. https://doi.org/10.52676/1729-7885-2018-3-117-121
9. Vityuk V.A., Vurim A.D., Kotov V.M., Vityuk G.A., Serre F., Payot F., Suteau C., Trotignon L. Development of a model fa for the study of emergency situation with an immediate blocking of the coolant flow in fast reactor // NNC RK Bulletin. –2018. – No. 3. – P. 93–98. (In Russ.) https://doi.org/10.52676/1729-7885-2018-3-93-98
10. Kaplienko, A.V., Lemekhov, V.V., Cherepnin, Y.S. et al. Tests of fuel elements with uranium-plutonium nitride fuel in an IGR pulsed reactor // Atom Energy. – 2023. – Vol. 134. – P. 275–282. https://doi.org/10.1007/s10512-024-01055-1
11. ANSYS, Inc. Products Release 2021 R1. Academic research Mechanical and CFD
12. MCNP-6.1. Monte-Carlo N-Particle Transport Code // Los Alamos National Laboratory; Los Alamos, New Mexico. – 2008.
13. Fluent A. et al. Ansys Fluent theory guide //Ansys Inc., USA. – 2021. 14. Batyrbekov E.G., Vurim A.D., Gaydaychuk V.A., Vityuk V.A. Impul'snyy grafitovyy reaktor: opyt ekspluatatsii i primeneniya dlya ispytaniy tvelov i TVS // Monografiya – Kurchatov, RK, 2023 g.
14. Vladimir Vityuk, Galina Vityuk, Alexander Vurim, Ruslan Irkimbekov, Ivan Kukushkin, Artur Surayev, Nurzhan Mukhamedov. Testing of a heterogeneous fuel rod in the research Impulse graphite reactor // Progress in Nuclear Energy. –2023. – Vol. 164. – art. No. 104889. https://doi.org/10.1016/j.pnucene.2023.104889
15. Kelsingazina R., Vityuk V., Vurim A., Vityuk G., Mukhamedov N., Tikhomirov G. Computational approaches for determining the nuclear heating value of structural materials during the irradiation at the IGR reactor // Annals of Nuclear Energy. – 2024. –Vol. 204. – art. No. 110532. https://doi.org/10.1016/j.anucene.2024.110532
16. Kabdylkakov Y.A., Suraev A.S. Application of the VOLUME OF FLUID method to simulate the process of melting and movement of fuel // NNC RK Bulletin. – 2021. – No. 3. – P. 3–8. (In Russ.) https://doi.org/10.52676/1729-7885-2021-3-3-8
17. Surayev A.S., Irkimbekov R.A., Vurim A.D. Modeling of the interaction of a melt jet with a steel wall // NNC RK Bulletin. – 2020. – No. 1. – P. 19–22. (In Russ.) https://doi.org/10.52676/1729-7885-2020-1-19-22
18. Tekhnicheskiy otchet o nauchno-issledovatel'skoy rabote. Analiz usloviy bezopasnogo provedeniya ispytaniy eksperimental'nogo ustroystva FD. Branch IAE RSE NNC RK. – Kurchatov, 2005.
19. Analiz rezul'tatov eksperimenta FD. Otchet po nauchnoissledovatel'skoy rabote // Branch IAE RSE NNC RK. – Kurchatov, 2006.
20. International Atomic Energy Agency. Thermophysical Properties of Materials for Nuclear Engineering: A Tutorial and Collection of Data. – 2008.
21. Haynes W. M. CRC handbook of chemistry and physics, (Internet Version 2011) //Taylor Francis Group: Boca Raton, FL. – 2011.
22. Chirkin, V.S. Teplofizicheskie svoystva materialov yadernoy tekhniki / V.S. Chirkin. – Moscow: Atomizdat, 1968. 121–128, 291–294, 237–239 p.
23. Manual U.D.F. ANSYS FLUENT 12.0 //Theory Guide. – 2021.
24. Eickhoff M., Rückert A., Pfeifer H. Solidification modeling with User defined function in Ansys Fluent //Progress in Applied CFD – CFD2017 Selected papers from 12th International Conference on Computational Fluid Dynamics in the Oil & Gas, Metallurgical and Process Industries. – SINTEF Academic Press, 2017.
25. Kabdylkakov Y., Surayev A., Irkimbekov R. New approaches to CFD analysis of experimental devices in the Ansys fluent // AIP Conference Proceedings. – AIP Publishing, 2024. – Vol. 3020. – No. 1.
26. Suleimenov N. A., Mukhamedov N. E., Zhanbolatov O. M. Using a user–defined function in ANSYS FLUENT to implement the energy release profile in model fuel elements taking into account radiation heating // Bulletin of the Karaganda University “Physics Series”. – 2021. – Vol. 104. – No. 4. – P. 78–84.
Review
For citations:
Kabdylkakov E.A., Suraev A.S., Zhanbolatov O.M., Vityuk G.A., Irkimbekov R.A. IMPROVEMENT OF METHODS FOR MODELING THE MELTING OF FUEL ASSEMBLIES IN THE CONDITIONS OF AN EXPERIMENT ON IGR RECTOR. NNC RK Bulletin. 2025;(2):151-164. (In Russ.) https://doi.org/10.52676/1729-7885-2025-2-151-164