Skip to main content
Log in

Simulating the retention of molten fuel in a fast-neutron reactor during a severe accident

  • Published:
Thermal Engineering Aims and scope Submit manuscript

Abstract

The problem of retaining molten fuel in the fast-reactor vessel during a severe accident is considered. A mathematical model implemented in the BRUT computer code is described and the calculated data obtained using this code are analyzed.

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. G. N. Vlasichev and G. B. Usynin, “A Model for Calculating Long-Term Axial Travel of Heat-Releasing Mass during an Accident Involving Meltdown of Fast Reactor’s Fuel Assemblies,” Izv. Vyssh. Uchebn. Zaved., Yadern. Energetika, No. 1, 97–105 (2000).

  2. K. Moor and J. Brealey, “Modeling of Sodium-Cooled Debris Beds,” in Proceedings of the International Conference on Science and Technology of Fast Reactor Safety, Guernsey, May 12–16, 1986 (BNES, London, 1987), Vol. 1, pp. 165–170.

    Google Scholar 

  3. V. I. Subbotin, V. M. Kashcheev, E. V. Nomofilov, and Yu. S. Yur’ev, Solving Reactor Thermal Physics Problems on a Computer (Atomizdat, Moscow, 1979) [in Russian.

    Google Scholar 

  4. M. V. Kashcheev and I. A. Kuznetsov, “Computation Analysis of Fuel Melt Confinement Processes in Fast Reactors,” in Proceedings of the International Conference on Fifty Years of Nuclear Power-the Next Fifty Years, Obninsk, Russian Federation, June 27–July 2, 2004, Paper IAEA-CN-114/35p.

  5. N. I. Nikitenko, Theory of Heat and Mass Transfer (Naukova Dumka, Kiev, 1983) [in Russian].

    Google Scholar 

  6. M. V. Kashcheev, “Simulating the Stratification of Corium Components during a Severe Accident,” Izv. Vyssh. Uchebn. Zaved., Yadern. Energetika, No. 3, 3–13 (2002).

  7. F. M. Mitenkov, V. F. Golovko, P. A. Ushakov, and Yu. S. Yur’ev, Designing Heat Exchangers for Nuclear Power Stations (Energoatomizdat, Moscow, 1988) [in Russian].

    Google Scholar 

  8. O. Kymäläinen, R. Tuomisto, O. Hongisto, and T. G. Theofanous, “Heat Flux Distribution from a Volumetrically Heated Pool with High Rayleigh Number,” in Proceedings of 6th International Topical Meeting on Reactor Thermal-Hydraulics, Grenoble, France, October 5–8, 1993, Vol. 1, pp. 47–53.

  9. A. V. Lykov, Heat Conductance Theory (Vysshaya Shkola, Moscow, 1967) [in Russian].

    Google Scholar 

  10. R. J. Lipinskii, J. E. Gronager, and M. Schwarz, “Particle Bed Heat Removal with Subcooled Sodium: D-4 Results and Analysis,” Nuclear Technology 58(3), 369–378 (1982).

    Google Scholar 

Download references

Author information

Authors and Affiliations

Authors

Additional information

Original Russian Text ¢ M.V. Kashcheev, I.A. Kuznetsov, 2007, published in Teploenergetika.

Rights and permissions

Reprints and permissions

About this article

Cite this article

Kashcheev, M.V., Kuznetsov, I.A. Simulating the retention of molten fuel in a fast-neutron reactor during a severe accident. Therm. Eng. 54, 955–961 (2007). https://doi.org/10.1134/S0040601507120038

Download citation

  • Issue Date:

  • DOI: https://doi.org/10.1134/S0040601507120038

Keywords

Navigation