Simulation of MCCI with the TOLBIAC-ICB code based on the phase segregation model

Nuclear Engineering and Design

Volumn 236, Issue 19-21, 2006, Pages 2264-2270

  Spindler, Bertrand ^a   Tourniaire, Bruno ^a   Seiler, Jean Marie ^a  

^a CEA GRENOBLE   (France)

Author keywords

[No Author keywords available]

Indexed keywords

COMPUTER SIMULATION; INTERFACIAL ENERGY; MOLTEN MATERIALS; NUCLEAR REACTOR ACCIDENTS; NUMERICAL ANALYSIS; RADIOACTIVE MATERIALS;

MOLTEN CORE CONCRETE INTERACTION (MCCI); PRESSURIZED WATER REACTOR; STRUCTURAL ELEMENTS; TOLBIAC-ICB CODE;

LIGHT WATER REACTORS;

EID: 33746654104     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2006.03.023     Document Type: Article

References (17)

1. Blottner, F.G., 1979. Hydrodynamics and heat transfer characteristics of liquid pools with bubble agitation, NUREG/CR-0944 Report.
2. Bonnet J.M. Thermal hydraulic phenomena in corium pools for ex-vessel situations: the BALI experiment. ICONE 8. Baltimore, USA, April (2000)
3. Bradley, D.R., Gardner, D.R., Brockmann, J.E., Griffith, R.O., 1993. CORCON-mod3: an integrated computer model for analysis of molten core-concrete interactions, NUREG/CR-5843 Report.
4. Commandé, A., 2003. ASTECV1 MEDICIS V1 MCCI module theoretical manual. ASTEC-V1/DOC/03-23 Report.
5. Epstein M., Petrie D.J., Linehan J.H., Lambert G.A., and Cho D.H. Incipient stratification and mixing in aerated liquid-liquid or liquid-solid mixtures. Chem. Eng. Sci. 36 4 (1981) 84-87
6. Farmer M.T., Lomperski S., and Basu S. Status of the melt coolability and concrete interaction (MCCI) program at Argonne National laboratory. Proceedings of the International Congress on Advances in Nuclear Power Plants ICAPP 05. Seoul, Korea, May (2005)
7. Journeau, C., 2003. A review of some corium physical properties, European Community. SAM-ECOSTAR-D23/02 Report.
8. Langhans, J., Spengler, C., Druwe, H., 2002. ASTEC V1, Description of WEX 3.1, improved version of WECHSL 3.5. ASTEC-V1/DOC/01-33 Report.
9. Kutateladze S.S., and Malenkov I.G. Boiling and bubbling heat transfer under the conditions of free and forced convection. Proceedings of the Sixth International Heat Transfer Conference. Toronto, Canada (1978)
10. Nie M., and Fischer M. Advanced MCCI modelling based on stringent coupling of thermal hydraulics and real solution thermochemistry in COSACO. Proceedings of the ICONE 10, 10th International Conference on Nuclear Engineering. Arlington, VA, April 14-18 (2002)
11. Piluso, P., 2003. CORPRO V1.5, Base de données propriétés physiques du corium, CEA.
12. Seiler J.M., and Froment K. Material effects on multiphase phenomena in late phases of severe accidents of nuclear reactors. Multiphase Sci. Technol. 12 2 (2000) 117-257
13. Seiler J.M., Fouquet A., Froment K., and Defoort F. Theoretical analysis for corium pool with miscibility gap. Nuclear Technol. 141 (2002) 233-243
14. Sudreau, F., Ramacciotti, M., Cognet, G., Seiler, J.M., Journeau, C., 2000. Calculation methodology for corium viscosity, European Commission Euratom Research Framework Program 1994-1998. Nuclear Fission Safety, INV-CIT(99)-P038 Report.
15. Tourniaire B., and Bonnet J.M. Study of the mixing of immiscible liquids by sparging gas; results of the BALISE experiments. Proceedings of the 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 10). Seoul, Korea, October 5-9 (2003)
16. Tourniaire B., and Seiler J.M. Modeling of viscous and inviscid fluid ejection through orifices by sparging gas. Proceedings of the International Congress on Advances in Nuclear Power Plants ICAPP 2004. Pittsburgh, PA, USA, June 13-17, Paper 4124 (2004)
17. Zuber N., and Findlay J.A. Average volumetric concentration in two-phase flow systems. J. Heat Transfer 87 C (1965) 453-462