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.
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REFERENCES
F. M. Mitenkov, “Concept and design solutions for new-generation reactors,” At. Énerg., 74, No. 4, 290–294 (1993).
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).
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).
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).
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).
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).
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).
J. McDonald and T. Connolly, “Investigation of natural convection heat transfer in liquid sodium,” Nucl. Sci. Eng., 8, No. 5, 369–377 (1960).
R. Lipinski, “A particle bed dryout model with upward and downward boiling,” Trans. ANS, 35, 358–360 (1980).
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.
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).
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).
J. Fink, M. Chasanov, and L. Leibowitz, “Thermophysical properties of uranium dioxide,” At. Tekh. Rubezh., No. 11, 20–25 (1982).
Thermophysical Properties of Alkali Metals, Izd. Standartov, Moscow (1970).
J. Rivard, “In-reactor experiments on the cooling of fast reactor debris,” Ncucl. Tech,, 46, No. 2, 344–349 (1979).
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).
Fast Reactor Database, IAEA, Vienna (1996).
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).
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).
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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
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DOI: https://doi.org/10.1023/A:1015814320039