NON-STANDARD APPROACHES TO FINITE ELEMENT MODELING OF IGR CORE

To model thermal processes that occur in the core of the Impulse Graphite Reactor (IGR), the Institute of Atomic Energy of the RSE NNC RK uses a designed three-dimensional thermophysical model. This model has a high degree of detail and allows for thermophysical calculations of the core parameters in various modes of operation, including at maximum energy release and in the event of emergency situations. The input data are multidimensional arrays with the distribution of energy release in the core, obtained after neutronic calculations. The result of the modeling is an array of data containing the temperature values of each unit of the model at each moment in time. When designing the thermophysical model, new non-standard approaches were implemented that were not previously used. This paper shows the features of modeling the IGR core in the ANSYS Mechanical APDL environment, which made it possible to obtain a high-quality tool for studying the temperature modes of the reactor.

1. Vityuk V., Vityuk G., Vurim A., Irkimbekov R., Kukushkin I., Surayev A., Mukhamedov N. Testing of a heterogeneous fuel rod in the research Impulse graphite reactor // Progress in Nuclear Energy. – 2023. – Vol. 164. – Art. no. 104889. ISSN 0149-1970, https://doi.org/10.1016/j.pnucene.2023.104889

2. 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 // OOI “Ishim”. – 2023. – 208 p. (In Russ.)

3. Khafizov R.R., Poplavsky V.M., Rachkov V.I., Sorokin A.P., Ashurko Yu.M., Volkov A.V., Ivanov E.F., Privezentsev V.V. Experimental investigation of sodium boiling heat exchange in fuel subassembly mockup for perspective fast reactor safety justification // Nuclear Energy and Technology. – 2015. – Vol. 1 (2). – P. 147–152. https://doi.org/10.26583/npe.2015.3.09

4. Erlan Batyrbekov, Vladimir Vityuk, Alexander Vurim, Galina Vityuk. Experimental opportunities and main results of the impulse graphite reactor use for research in safety area // Annals of Nuclear Energy. – 2023. – Vol. 182. – 109582. https://doi.org/10.1016/j.anucene.2022.109582

5. A.S. Surayev, R.A. Irkimbekov, Z.B. Kozhabayev, V.A. Vityuk Impact assessment of the IGR graphite block uneven impregnation with uranium on thermal strength properties / Recent Contributions to Physics. – 2022. – No. 3(82). – P. 52–59. https://doi.org/10.26577/RCPh.2022.v82.i3.08

6. ANSYS, Inc. Products Release 2021 R1. Academic research Mechanical and CFD

7. Bekmagambetova B.Ye., Vurim A.D., Irkimbekov R.A., Surayev A.S. IGR reactor temperature field dynamics // NNC RK Bulletin. – 2018. – Vol. 4. – P. 60–65. (In Russ.) https://doi.org/10.52676/1729-7885-2018-4-60-65

8. ANSYS Mechanical APDL. Thermal Analysis Guide, Ansys Inc., November, 2013.

9. Rajashekaraiah T. et al. Investigating Various Meshing Techniques in Computational Fluid Dynamics (CFD) for their Impact on Heat Transfer Parameters of Fins // Journal of Mines, Metals and Fuels. – 2025. – P. 117–128. https://doi.org/10.18311/jmmf/2025/45417

10. Vick, Paul. 2004. The Visual Basic .Net Programming Language. Addison-Wesley Professional.

11. Irkimbekov, R. A., Vityuk, V. A., Vityuk, G. A., Zhanbolatov, O. M., Surayev, A. S., Popov, Y. A., & Kotlyar, A. N. Development of a new computational support tool for experiments in the impulse graphite reactor // Nuclear Engineering and Design. – 2025. – Vol. 443. – Art. no. 114278. https://doi.org/10.1016/j.nucengdes.2025.114278