Skip to main content
Log in

Computational Analysis of Heat Removal from the Core-Melt Catcher in a BN-800 Vessel in the Case of a Serious Unanticipated Accident

  • Published:
Atomic Energy Aims and scope

Abstract

A numerical analysis is performed of the cooling efficiency of a bed consisting of fragments of a destroyed core on a BN-800 catcher. A stationary model of the effective thermal conductivity is used to calculate the vertical distribution of the temperature in a heat-releasing layer, including a porous layer located in the coolant, taking account of the aggregate state of the components. The ST0-BED code is tested on numerical results obtained using explicit expressions derived from an analytical solution. The physical accuracy of the method is checked on the results of series-D experiments performed at the Sandia Laboratories in the USA. The numerical estimates show that the cooling of the heat-releasing mass consisting of fuel and the source material of the core assemblies on the BN-800 catcher occurs in the case of a serious accident with heat release density corresponding to 5.5 h after the reactor becomes subcritical. The maximum temperature in the bed at this time will be lower than the boiling temperature of the fuel. The temperature on the catcher is 650–900°C.

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. F. M. Mitenkov, “Concept and design solutions for new-generation reactors,” At. Énerg., 74, No. 4, 290–294 (1993).

    Google Scholar 

  2. N. I. Ermakov, V. N. Murogov, M. F. Troyanov, et al., “Fast reactors: design, construction, and operation experience, growth prospects,” ibid., 76, No. 4, 339–345 (1994).

    Google Scholar 

  3. L. A. Kochetkov, A. I. Kiryushin, and N. N. Oshkanov, “Fast sodium-cooled reactors in Russia - view beyond 2000,” ibid., 74, No. 4, 282–285 (1993).

    Google Scholar 

  4. R. Nijsing and S. Schwalm, “A one-dimensional computational method for predicting the asymptotic heat transfer behavior of sodium-saturated fuel particle beds with top and bottom cooling,” Nucl. Eng. Des., 66, 151–170 (1981).

    Google Scholar 

  5. G. N. Vlasichev, “Method for calculating the temperature of a saturated layer consisting of fragments of a destroyed core,” Inzh.-Fiz. Zh., 69, No. 2, 243–254 (1996).

    Google Scholar 

  6. H. Kampf and G. Karsten, “Effects of different types of void volumes on the radial temperature distribution of fuel pins,” Nucl. App. Tech., 9, No. 3, 288–300 (1970).

    Google Scholar 

  7. R. Lipinski, J. Gronager, and M. Schwarz, “Particle bed heat removal with subcooled sodium: D4 results and analysis,” Nucl. Tech., 58, No. 3, 369–378 (1982).

    Google Scholar 

  8. J. McDonald and T. Connolly, “Investigation of natural convection heat transfer in liquid sodium,” Nucl. Sci. Eng., 8, No. 5, 369–377 (1960).

    Google Scholar 

  9. R. Lipinski, “A particle bed dryout model with upward and downward boiling,” Trans. ANS, 35, 358–360 (1980).

    Google Scholar 

  10. Yu. K. Buksha and E. E. Marinenko, “Analysis of coolability of fast reactor core debris,” in: Sodium Cooled Fast Reactor Safety. Proceedings of International Topical Meeting, Obninsk, Russia, October 3- 7, 1994, Obninsk (1994), Vol. 2, pp. 2/4–2/13.

    Google Scholar 

  11. H. Godbee and W. Ziegler, “Thermal conductivities of MgO, Al2O3, and ZrO2 powders to 850°C. II. Theoretical,” J. Appl. Phys., 37, No. 1, 56–65 (1966).

    Google Scholar 

  12. P. L. Kirillov, Yu. S. Yur'ev, and V. P. Bobkov, In: Handbook of Thermohydraulic Calculations (Nuclear Reactors, Heat Exchangers, Steam Generators), P. L. Kirillov (ed.), Énergoatomizdat, Moscow (1984).

    Google Scholar 

  13. J. Fink, M. Chasanov, and L. Leibowitz, “Thermophysical properties of uranium dioxide,” At. Tekh. Rubezh., No. 11, 20–25 (1982).

    Google Scholar 

  14. Thermophysical Properties of Alkali Metals, Izd. Standartov, Moscow (1970).

  15. J. Rivard, “In-reactor experiments on the cooling of fast reactor debris,” Ncucl. Tech,, 46, No. 2, 344–349 (1979).

    Google Scholar 

  16. T. Fujii, H. Honda, and I. Morioka, “A theoretical study of natural convection heat transfer from downward-facing horizontal surfaces with uniform heat flux,” Intern. J. Heat and Mass Transfer, 16, No. 3, 611–627 (1973).

    Google Scholar 

  17. Fast Reactor Database, IAEA, Vienna (1996).

  18. G. N. Blasichedv, G. B. Usynin, and N. G. Kuzavkov, “Computational investigation of the movement of a fused mass to the vessel bottom during an unanticipated accident in a fast reactor,” At. Énerg., 77, No. 3, 180–185 (1994).

    Google Scholar 

  19. M. El-Genk, D. Louie, R. Lipinski, and D. Mitchell, “Experimental measurements of porosity and capillary pressure in particulate beds,” Trans. ANS, 44, 337–339 (1983).

    Google Scholar 

Download references

Author information

Authors and Affiliations

Authors

Rights and permissions

Reprints and permissions

About this article

Cite this article

Vlasichev, G.N., Kuzavkov, N.G. Computational Analysis of Heat Removal from the Core-Melt Catcher in a BN-800 Vessel in the Case of a Serious Unanticipated Accident. Atomic Energy 92, 100–109 (2002). https://doi.org/10.1023/A:1015814320039

Download citation

  • Issue Date:

  • DOI: https://doi.org/10.1023/A:1015814320039

Keywords

Navigation