Skip to main content
Log in

Calculation of the Flow Parameters in the Fuel Bundles of FA with Spacers by Means of the Conv-3D Code

  • Published:
Atomic Energy Aims and scope

The results of modeling performed with the CONV-3D code of incompressible fluid flow in the fuel-rod bundles of fuel assemblies with spacer grids are presented. The simulation results are presented for different Reynolds numbers and lattice spacing in comparison with experiments. It is shown that the code satisfactorily simulates incompressible fluid flow in the fuel-rod bundles of fuel assemblies with spacers and can be used to analyze such flows in various applications.

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.

Similar content being viewed by others

References

  1. A. C. Devkin, O. I. Melikhov, A. M. Moskalev, et al., Foreign Improved-Accuracy Thermohydraulic Codes: Development Experience, Origination, and Application, OTsRK at Ministry of Atomic Energy of the Russian Federation, Moscow (2000).

  2. V. V. Chudanov, A. E. Aksenova, A. A. Makarevich, et al., “Use of the CFD-сode CONV-3D in reactor applications,” At. Energ., 121, No. 3, 140–143 (2016); Atomic Energy, 121, No. 3, 179–184 (2017).

  3. Yu. G. Dragunov, S. B. Ryzhov, I. N. Vasil’chenko, et al., “Core design for the NPP-2006 reactor plant,” in: 5th Int. Sci. Techn. Conf. on Safety Security of NPP with VVER, Podolsk, May 29 – June 1, 2007, OKB Gidropress, No. 140.

  4. J. Pacio, M. Daubner, F. Fellmoser, et al., “Heavy-liquid metal heat transfer experiment in a 19-rod bundle with grid spacers,” Nucl. Eng. Des., 273, 33–46 (2014).

    Article  Google Scholar 

  5. Precision Scalable Vortex-Resolving CFD-Module Based on DNS-Approximation, Focused on Petaflops Computers for Reactor Plants with Different Types of Coolant. Educational Version 1.0, CONV-3/V2/1.0, IBRAE RAS, Moscow (2018).

  6. P. L. Kirillov, Handbook of Thermohydraulic Calculations in Nuclear Power, Vol. 3, Thermal-Hydraulic Processes in Transient and Non-Standard Regimes. Severe Accidents. Containment. Codes, Their Capabilities, Uncertainties, IzdAT, Moscow (2014).

  7. V. V. Chudanov, A. E. Aksenova, and V. A. Pervichko, “CONV-3D code aided calculation of the flow parameters of fuel-rod bundles,” At. Energ., 128, No. 5, 268–270 (2020); Atomic Energy, 128, No. 5, 287–290 (2020).

Download references

Author information

Authors and Affiliations

Authors

Corresponding author

Correspondence to V. V. Chudanov.

Additional information

Translated from Atomnaya Énergiya, Vol. 130, No. 5, pp. 293–295, May, 2021.

Rights and permissions

Reprints and permissions

About this article

Check for updates. Verify currency and authenticity via CrossMark

Cite this article

Chudanov, V.V., Aksenova, A.E. & Pervichko, V.A. Calculation of the Flow Parameters in the Fuel Bundles of FA with Spacers by Means of the Conv-3D Code. At Energy 130, 310–313 (2021). https://doi.org/10.1007/s10512-021-00815-7

Download citation

  • Received:

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1007/s10512-021-00815-7

Navigation