Numerical simulation of a hypothetical core disruptive accident in a small-scale model of a nuclear reactor

Nuclear Engineering and Design

Volumn 223, Issue 2, 2003, Pages 159-196

  Robbe, M F ^a   Lepareux, M ^a   Treille, E ^b   Cariou, Y ^c  

^a CEA SACLAY   (France)

^b Socotec Industrie   (France)

^c NVPM   (France)

Author keywords

[No Author keywords available]

Indexed keywords

COMPUTER SIMULATION; COOLING; CORE DISRUPTIVE ACCIDENTS; DEFORMATION; FLOW OF FLUIDS; NUMERICAL METHODS;

REACTOR VESSELS;

REACTOR CORES;

EID: 0037705353     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(03)00039-6     Document Type: Article

References (56)

1. Acker, D., Benuzzi, A., Yerkess, A., Louvet, J., 1981. MARA 01/02 - experimental validation of the SEURBNUK and SIRIUS containment codes. In: Proceedings of the Sixth International Conference on Structural Mechanics in Reactor Technology, Paper E 3/6, Paris, France.
2. Albertini, C., Benuzzi, A., Delaval, M., Delzano, C., Fasoli Stella, P., Holtbecker, H., Jones, A.V., Magonette, G.E., Montagnani, M., Verzeletti, G., Yerkess, A., 1984. The JRC-COVA programme: final report, Commission of the European Communities, report EUR 8705, 1983. Nucl. Sci. Technol. 1-182.
3. Benuzzi A., Comparison of different LMFBR primary containment codes applied to a benchmark problem. Nucl. Eng. Des. 100:1987;239-249.
4. Blanchet, Y., Obry, P., Louvet, J., 1981. Treatment of fluid-structure interaction with the SIRIUS computer code. In: Proceedings of the Sixth International Conference on Structural Mechanics in Reactor Technology, Paper B 8/8, Paris, France.
5. Bour, C., Spérandio, M., Louvet, J., Rieg, C., 1989. LMFBR's core disruptive accident. Mechanical study of the reactor block. In: Proceedings of the 10th International Conference on Structural Mechanics in Reactor Technology, vol. E, Anaheim, USA, pp. 281-287.
6. Bung, H., Casadei, F., Halleux, J.P., Lepareux, M., 1989. PLEXIS-3C: a computer code for fast dynamic problems for structures and fluids. In: Proceedings of the 10th International Conference on Structural Mechanics in Reactor Technology, vol. B, Anaheim, USA, pp. 85-90.
7. Cagliostro D.J., Florence A.L., Abrahamson G.R., Scale modeling in LMFBR safety. Nucl. Eng. Des. 55:1979;235-247.
8. Cameron, I.G., Hankin, B.C., Warham, A.G.P., Benuzzi, A., Yerkess, A., 1977. The computer code SEURBNUK-2 for fast reactor explosion containment safety studies. In: Proceedings of the Fourth International Conference on Structural Mechanics in Reactor Technology, Paper B 2/1, San Francisco, USA.
9. Cariou, Y., Spérandio, M., Lepareux, M., Christodoulou, K., 1993. LMFBR's whole core accident. Validation of the PLEXUS code by comparison with MARA tests. In: Proceedings of the 12th International Conference on Structural Mechanics in Reactor Technology, Paper E 7/4, Stuttgart, Germany.
10. Cariou, Y., Pirus, J.P., Avallet, C., 1997. LMR large accident analysis method. In: Proceedings of the 14th International Conference on Structural Mechanics in Reactor Technology, Paper P 3/7, Lyon, France, pp. 395-402.
11. Casadei, F., Daneri, A., Toselli, G., 1989. Use of PLEXUS as a LMFBR primary containment code for the CONT benchmark problem. In: Proceedings of the 10th International Conference on Structural Mechanics in Reactor Technology, Paper E 13/1, Anaheim, USA, pp. 299-304.
12. Chang Y.W., Application of containment codes to LMFBRs in the United States. Nucl. Eng. Des. 42:1977;53-67.
13. Chang Y.W., Gvildys J., Fistedis S.H., Analysis of the primary containment response using a hydrodynamic-elastic-plastic computer code. Nucl. Eng. Des. 27:1974;155-175.
14. Chavant, C., Hoffmann, A., Verpeaux, P., Dubois, J., 1979. Plexus: a general computer code for explicit Lagrangian computation. In: Proceedings of the Fifth International Conference on Structural Integrity in Reactor Technology, Paper B 2/8, Berlin, Germany.
15. Cigarini, M., Daneri, A., Toselli, G., 1983. Applications of ASTARTE-4 code to explosive models with complex internal structure using the rezoning facility. In: Proceedings of the Seventh International Conference on Structural Mechanics in Reactor Technology, Paper B 9/3, Chicago, USA.
16. Cowler, M.S., Hancock, S.L., 1979. Dynamic fluid-structure analysis of shells using the PISCES 2 DELK computer code. In: Proceedings of the Fifth International Conference on Structural Mechanics in Reactor Technology, Paper B 1/6, Berlin, Germany.
17. Daneri, A., Toselli, G., Trombetti, T., Blanchet, Y., Louvet, J., Obry, P., 1981. Influence of the representation models of the stress-strain law on the LMFBR structures in an HCDA. In: Proceedings of the Sixth International Conference on Structural Integrity in Reactor Technology, Paper E 4/4, Paris, France.
18. David, F., 1978. Etude d'une composition explosive flegmatisée. Applications à la déformation d'une cuve. In: Proceedings of the Symposium sur les Hautes Pressions Dynamiques, Paris, France.
19. Falgayrettes, M., Fiche, C., Granet, P., Hamon, P., Barrau, P., Magnon, B., Jalouneix, J., Nédélec, M., 1983. Response of a 1/20 scale mock-up of the Superphenix breeder reactor to an HCDA loading simulation. In: Proceedings of the Seventh International Conference on Structural Mechanics in Reactor Technology, Paper E 4/1, Chicago, USA, pp. 157-166.
20. Fiche, C., Louvet, J., Smith, B.L., Zucchini, A., 1985. Theoretical experimental study of flexible roof effects in an HCDA's simulation. In: Proceedings of the Eighth International Conference on Structural Integrity in Reactor Technology, Paper E 4/5, Brussels, Belgium, pp. 139-144.
21. Graveleau, J.L., Louvet, P., 1979. Calculation of fluid-structure interaction for reactor safety with the CASSIOPEE code. In: Proceedings of the Fifth International Conference on Structural Mechanics in Reactor Technology, Paper B 1/7, Berlin, Germany.
22. Hoffmann, A., Lepareux, M., Schwab, B., Bung, H., 1984. Plexus: a general computer program for fast dynamic analysis. In: Proceedings of the Conference on Structural Analysis and Design on Nuclear Power Plant, Porto Alegre, Brazil.
23. Holtbecker H., Testing philosophy and simulation techniques. Nucl. Eng. Des. 42:1977;75-87.
24. Hoskin N.E., Lancefield M.J., The COVA programme for the validation of computer codes for fast reactor containment studies. Nucl. Eng. Des. 46:1978;17-46.
25. Kendall, K.C., Adnams, D.J., 1986. Experiments to validate structural dynamics code used in fast reactor safety assessment. In: Science and Technology of Fast Reactor Safety, vol. 2. British Nuclear Energy Society, London, UK.
26. Kendall K.C., Benuzzi A., The COVA programme: validation of the fast reactor containment code SEURBNUK. Nucl. Eng. Des. 57:1980;79-105.
27. Lepareux, M., Schwab, B., Hoffmann, A., Jamet, P., Bung, H., 1985a. Un programme général pour l'analyse dynamique rapide - cas des tuyauteries. In: Proceedings of the Colloque Tendances Actuelles en Calcul des Structures, Bastia, France.
28. Lepareux, M., Schwab, B., Bung, H., 1985b. Plexus: a general computer program for the fast dynamic analysis. The case of pipe-circuits. In: Proceedings of the Eighth International Conference on Structural Mechanics in Reactor Integrity, Paper F1 2/1, Brussels, Belgium.
29. Lepareux, M., Bung, H., Combescure, A., Aguilar, J., 1991. Analysis of a CDA in a LMFBR with a multiphasic and multicomponent behaviour law. In: Proceedings of the 11th International Conference on Structural Mechanics in Reactor Integrity, Paper E 13/1, Tokyo, Japan, pp. 371-376.
30. Lepareux, M., Bung, H., Combescure, A., Aguilar, J., Flobert, J.F., 1993. Analysis of an HCDA in a fast reactor with a multiphase and multicomponent behavior law. In: Proceedings of the 12th International Conference on Structural Mechanics in Reactor Integrity, Paper E 7/2, Stuttgart, Germany, pp. 197-202.
31. Lepareux, M., Michelin, J.M., Thiault, D., 1994. Plexus-R: une extension de Plexus à la robotique, CEA report DMT/94-138.
32. Louvet, J., 1989. Containment response to a core energy release. Main experimental and theorical issues. Future trends. In: Proceedings of the 10th International Conference on Structural Mechanics in Reactor Integrity, vol. E, Anaheim, USA, pp. 305-310.
33. Louvet, J., Hamon, P., Smith, B.L., Zucchini, A., 1987. MARA 10: an integral model experiment in support of LMFBR containment analysis. In: Proceedings of the Ninth International Conference on Structural Mechanics in Reactor Integrity, vol. E, Lausanne, Switzerland, pp. 331-337.
34. NERSA, 1987. The Creys-Malville power plant, Electricité de France, Direction de l'équipement, Région d'équipement Alpes-Lyon, France.
35. Robbe M.F., Bliard F., A porosity method to describe the influence of internal structures on a fluid flow in case of fast dynamics problems. Nucl. Eng. Des. 215:2002;217-242.
36. Robbe M.F., Lepareux M., Evaluation of the mechanical consequences of a steam explosion in a nuclear reactor. Bulg. J. Theor. Appl. Mech. 32(n) ° 1:2002;48-84.
37. Robbe, M.F., Potapov, S., 2003. Modeling of the depressurisation induced by a pipe rupture in the primary circuit of a nuclear plant. Rev. Eur. Eléments Finis, in preparation.
38. Robbe, M.F., Lepareux, M., Bung, H., 1994. Plexus - notice théorique, CEA report DMT/94-490.
39. Robbe, M.F., Galon, P., Yuritzinn, T., 1999. Castem-Plexus: un logiciel de dynamique rapide pour évaluer l'intégrité des structures en cas d'accident. In: Proceedings of the Fourth Conference INSTRUC, Courbevoie, France, pp. 224-233.
40. Robbe, M.F., Cariou, Y., Lepareux, M., Treille, E., 2000a. Numerical interpretation of the MARA 10 test simulating a Hypothetical Core Disruptive Accident in a mock-up schematizing a reactor. In: Proceedings of the Eighth International Conference on Numerical Methods in Continuum Mechanics, Liptovský Ján, Slovak Republic, CD-ROM.
41. Robbe, M.F., Cariou, Y., Treille, E., Lepareux, M., 2000b. Qualification of the numerical simulation of a Hypothetical Core Disruptive Accident on the MARA 10 mock-up. In: Proceedings of the International Colloquium in Mechanics of Solids, Fluids, Structures and Interactions, Nha Trang, Vietnam, pp. 745-755.
42. Robbe M.F., Vivien N., Valette M., Berglas E., Use of thermalhydraulic and mechanical linked computations to estimate the mechanical consequences of a steam explosion. J. Mech. Eng. 52(n) ° 2:2001a;65-90.
43. Robbe, M.F., Treille, E., Cariou, Y., Lepareux, M., 2001b. Simulation of a Core Disruptive Accident in the scale model MARA 10 schematizing a reactor. In: Proceedings of the ANS/HPS Student Conference, "2001: A Nuclear Odyssey", A&M University, Texas, USA, CD-ROM.
44. Robbe M.F., Lepareux M., Treille E., Cariou Y., Numerical simulation of an explosion in a simple scale model of a nuclear reactor. J. Comput. Assist. Mech. Eng. Sci. 9(n) ° 4:2002a;489-517.
45. Robbe M.F., Lepareux M., Trollat C., Hydrodynamic loads on a PWR primary circuit due to a LOCA. Nucl. Eng. Des. 211:2002b;189-228.
46. Robbe, M.F., Lepareux, M., Cariou, Y., 2002c. Estimation of the consequences of a Core Disruptive Accident in the small-scale mock-up MARA 10 representing a LMFBR. In: Proceedings of the European Nuclear Conference, Lille, France, CD-ROM.
47. Robbe M.F., Lepareux M., Treille E., Cariou Y., Numerical interpretation of the MARA 8 experiment simulating a Hypothetical Core Disruptive Accident. Nucl. Eng. Des. 220:2003c;119-158.
48. Robbe, M.F., Potapov, S., Teffany, F., 2003b. Simulation of the depressurisation occuring at the beginning of a LOCA in a 4-loop PWR. Nucl. Eng. Des., in preparation.
49. Sidoli, J.E.A., Kendall, K.C., 1988. The WINCON programme. Validation of the fast reactor primary containment codes. In: Proceedings of the INE International Conference on Nuclear Containment Structures, D.G. Walton, Cambridge University Press.
50. Smith, B.L., Yerkess, A., Adamson, J., 1983. Status of coupled fluid-structure dynamics code SEURBNUK. In: Proceedings of the Seventh International Conference on Structural Mechanics in Reactor Technology, Paper B 9/1, Chicago, USA.
51. Smith, B.L., Fiche, C., Louvet, J., Zucchini, A., 1985. A code comparison exercise based on the LMFBR containment experiment MARA-04. In: Proceedings of the Eighth International Conference on Structural Mechanics in Reactor Technology, Paper E 4/7, Brussels, Belgium, pp. 151-157.
52. Smith, B.L., Yerkess, A., Washby, V., 1987. The computer code SEURBNUK-EURDYN: first release version. In: Proceedings of the Ninth International Conference on Structural Mechanics in Reactor Technology, Lausanne, Switzerland.
53. Stiévenart, M., Bouffioux, P., Eglème, M., Fabry, J.P., Lamotte, H., 1975. Analysis of LMFBR explosion model experiments by means of the Surboum-II code. In: Proceedings of the Third International Conference on Structural Mechanics in Reactor Technology, Paper E 3/5, London, UK.
54. Struder E., Galon P., Hydrogen combustion loads - Plexus calculations. Nucl. Eng. Des. 174:1997;119-134.
55. Wenger, H.U., Smith, B.L., 1987. On the origin of the discrepancies between theory and experiment in the COVA series. In: Proceedings of the Ninth International Conference on Structural Mechanics in Reactor Technology, vol. E, Lausanne, Switzerland, pp. 339-344.
56. West, P.H., Hoskin, N.E., 1980. APRICOT - Phase 3. Suggested simple test problems for examination of thin shell modelling and fluid structure coupling, Aldermaston report AWRE/44/92/16.