Abstract
Chapter 15 is devoted to the coolability of layers of molten nuclear reactor material. Such physics is important for designing of stabilization of spread melt in reactor compartments. After defining the problem with its boundary conditions and some simplifying assumptions the system of differential equations describing the process is presented: mass and energy conservation. The following effects are taken into account: the molten steal dropped in the melt or originating inside the melt; the gas release from a sub-layer; the viscous layer; the crust formation; the buoyancy driven convection; the film boiling; the heat conduction through the structures; oxide crust formation on colder heat conducting structures. The existence of a metallic layer is also considered. Some test cases are presented to make easy the application of the presented models: oxide over metal and oxide besides metal. A simple model for gravitational flooding of hot solid horizontal surface by water leading to hyperbolic system is also presented.
Access this chapter
Tax calculation will be finalised at checkout
Purchases are for personal use only
Preview
Unable to display preview. Download preview PDF.
References
Alsmeier, H., et al.: COMMET-Konzept, Chap. 6.1. In B. Mühl, ed., Forschungszentrum Karlsruhe, Technik and Umwelt. Untersuchungen zu auslegungsüberschreitenden Ereignissen (Unfällen) in Leichtwasserreaktoren (März 1997)
Berenson, P.J.: Film-boiling heat transfer from a horizontal surface. J. Heat Transfer 83, 351–361 (1961)
Fish, J.D., Pilch, M., Arellano, F.E.: Demonstration of passively-cooled particle-bed core retention. In: Proceedings of the LMFBR Safety Topical Meeting, Lyon, Ecully France, pp. III-327–336 (July 1982)
Friedrich, H.J.: SNR-300 Tank external core retention device design and philosophy behind it. In: Coats RL ed., The Second Annual Post – Accident Heat Removal (PAHR) Information Exchange, SAND76-9008, p 333 (November 13–14, 1975)
Friedrich, H.J.: Dynamic behavior of SNR-300 core retention device in experimental support of the design concept. In: Baker, L., Bingle, J.D. (eds.) Proceedings of the Third Post-Accident Heat Removal Information Exchange, ANL-78-10, (November 2-4, 1977)
Gandrille, P.: Input data for severe accident mitigation measures. Nuclear System Supply System Part, FRA Report EPTA DC 1476, Rev. A (April 4, 1997)
Hübel, H.J.: The safety related criteria and design features for SNR. In: Proceedings Fast Reactor Safety Meeting, Beverly Hills CONF-740401-P1, pp. 3–21 (April 1974)
Kolev, N.I.: Transiente Zweiphasenströmung (Transient Two-Phase Flow), ch. 4, pp. 34–38. Springer, Heidelberg (1986)
Kolev, N.I.: External Cooling of EPR 1500 Reactor Vessel under Severe Accident Conditions, Part 1. Buoyancy driven convection, metallic layer dynamics, wall ablation, KWU NA-M/95/E030, Project R&D (April 20, 1995a)
Kolev, N.I.: IVA4 Computer code: The model for a film boiling on a sphere in subcooled, saturated and superheated water. In: The Second International Conference on Multiphase Flow, 1995-Kyoto, April 3-7 (1995b)
Kolev, N.I.: Gravitational flooding of hot solid horizontal surface by water. Kerntechnik 61, 67–76 (1996)
Kutateladse, S.S.: A hydrodynamic theory of changes in the boiling process under free convection conditions. Izv. Akad. Nauk SSSR, Otd. Tech. Nauk 4, 529–536 (1951); AEC-tr-1991 (1954)
Kolev, N.I.: External cooling Of PWR reactor vessel during severe accident. Kerntechnik 61(2-3), 67–76 (1996); abbreviated form in Proceedings of ICONE-4, The Fourth International Conference on Nuclear Engineering, New Orleans, USA (March 8-12, 1996)
Kolev, N.I.: IVA4 Layers vol 2 A computer code for analysis of coolability of molten reactor materials spread as a horizontal layers, KWU NA-M/1997/E050, Project R&D (October 6,1997)
Kolev, N.I.: Verification of the IVA4 film boiling model with the data base of Liu and Theofanous. In: Proceedings of OECD/CSNI Specialists Meeting on Fuel-Coolant Interactions (FCI), JAERI-Tokai Research Establishment, Japan (May 19-21,1997)
Kolev, N.I.: Computational analysis of transient 3D-melt-water interactions. In: 8th International Conference on Nuclear Engineering, Baltimore, Maryland USA, ICONE-8809, April 2-6 (2000a)
Kolev, N.I.: Needs of industrial fluid dynamics applications. In: 2000 ASME Fluids Engineering Division Summer Meeting (FEDSM), Industry Exchange Program, Sheraton Boston Hotel, Boston, Massachusetts, June 11-15 (2000b)
Kulacki, F.A., Goldstein, R.J.: Thermal convection in a horizontal fluid layer with uniform volumetric energy source. J. Fluid Mech. 55(2), 271–287 (1972)
Mayinger, F., Jahn, M., Reineke, H.H.: U. Steinberner, Untersuchung thermodynamischer Vorgänge sowie Wärmeaustausch in der Kernschmelze, Teil 1: Zusammenfassende Darstellung der Ergebnisse, Bundesministerium für Forschung und Technologie, Arbeitsbericht BMFT – RS 48/1 (1975)
Müller, U., Schulenberg, T.: Post accident heat removal research: A state of the art review, KfK 3601, Report Kernforschungszentrum Karlsruhe (November 1983)
Richard, P., Szabo, I.: In-vessel core retention study: Proposal for a core-catcher concept. In: Proceedings of the ICON 5: 5th International Conference on Nuclear Engineering, Nice, France, ICONE5-2156 (May 26-30, 1997)
Savino, J.M., Siegel, R.: An analytical solution for solidification of moving warm liquid onto an isothermal cold wall. Int. J. Heat Mass Transfer 12, 803–809 (1968)
Swanson, D.G., Cotton, I., Dhir, V.K.: A Thoria Rubble Bed for Post Accident Core Retention. In: Müller, U., Günter, C. (eds.) Post-Accident Debris Cooling. Proceedings of the Fifth Post Accident Heat Removal Information Exchange Meeting, G. Braun, Karlsruhe, pp. 307–312 (1982, 1983); ISBN3 – 7650-2034-6
VDI-Wärmeatlas, Berechnungsblätter für den Wärmeübergang, Sechste Auflage, VDI Verlag, Düsseldorf (1991)
Zuber, N., Findlay, J.A.: Averaged volumetric concentration in the two-phase flow systems. J. Heat Transfer 87, 453 (1965)
Rights and permissions
Copyright information
© 2011 Springer-Verlag Berlin Heidelberg
About this chapter
Cite this chapter
Kolev, N.I. (2011). Coolability of layers of molten reactor material. In: Multiphase Flow Dynamics 5. Springer, Berlin, Heidelberg. https://doi.org/10.1007/978-3-642-20601-6_15
Download citation
DOI: https://doi.org/10.1007/978-3-642-20601-6_15
Publisher Name: Springer, Berlin, Heidelberg
Print ISBN: 978-3-642-20600-9
Online ISBN: 978-3-642-20601-6
eBook Packages: EngineeringEngineering (R0)