Feasibility study mixed oxide fuel tests in the impulse graphite reactor

Authors

  • G. A. Vityuk Author
  • V.A. Vityuk Author
  • A.D. Vurim Author
  • M.K. Skakov Author
  • A.V. Gradoboyev Author

Abstract

The article presents the results of computational studies to substantiate the possibility of testing the fuel of the Multipurpose hYbrid Research Reactor for a High-tech Applications reactor (MYRRHA) in the Impulse Graphite research Reactor (IGR). A scheme for conducting experiments is proposed, which allows simulating the operating conditions of MYRRHA fuel elements in a wide range of changes in their thermohydraulic parameters, including the conditions of accidents with the destruction of fuel pellets, blocking the flow area and stopping the coolant flow. A method for thermohydraulic calculations has been developed, implemented in the software environment of the computational fluid dynamics (CFD) code. A computational model of the experimental device is developed, optimized according to the spatial partitioning grid. A turbulence model for determining the parameters of convective heat and mass transfer in a eutectic lead-bismuth alloy is selected and substantiated. © 2022, Eurasian Journal of Physics and Functional Materials. All Rights Reserved.

Recommended Citation

Vityuk, G. A.; Vityuk, V. A.; Vurim, A. D.; Skakov, M. K.; and Gradoboyev, A. V. (2022) "Feasibility study mixed oxide fuel tests in the impulse graphite reactor," Eurasian Journal of Physics and Functional Materials: Vol. 6: No. 3, Article 5.
DOI: https://doi.org/10.32523/ejpfm.2022060305

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Published

2026-03-06

How to Cite

(1)
Vityuk, G.; Vityuk, V.; Vurim, A.; Skakov, M.; Gradoboyev, A. Feasibility Study Mixed Oxide Fuel Tests in the Impulse Graphite Reactor. Eur. J. Phys. Funct. Mater. 2026, 6 (3).