Numerical simulation of an explosion in a small-scale replica of a Fast Breeder Reactor

• Autorzy: Robbe M. F. , Lepareux M. , Cariou Y. , Treille E.
• Języki publikacji: EN

Abstrakty

EN

A Core Disruptive Accident in a Liquid Metal Fast Breeder Reactor (LMFBR) results from the interaction between molten fuel and liquid sodium, which creates a high-pressure bubble of gas in the core. The violent expansion of this bubble loads and deforms the vessel and the internal structures. The MARS experimental test simulates a hypothetical Core Disruptive Accident in a small-scale mock-up containing all the significant internal components of a LMFBR. This paper presents a numerical simulation of the test with the EUROPLEXUS code.

Słowa kluczowe

EN

fast breeder reactor; numerical modelling

• Wydawca: Instytut Podstawowych Problemów Techniki PAN
• Czasopismo: Computer Assisted Mechanics and Engineering Sciences
• Rocznik: 2005
• Tom: Vol. 12, No. 4
• Strony: 413--442
• Opis fizyczny: Bibliogr. 60 poz., rys.

Twórcy

autor

Robbe M. F.

• CEA Saclay, Bat 118, 91191 Gif sur Yvette cedex, France

autor

Lepareux M.

• CEA Saclay, SEMT-DYN, 91191 Gif sur Yvette cedex, France

autor

Cariou Y.

• Novatome, NVPM, 10 rue Juliette Récamier, 69006 Lyon, France

autor

Treille E.

• Scotec Industrie, 1 av. du Parc, 78180 Montigny le Bretonneux, France

Bibliografia

• [1] D. Acker, A. Benuzzi, A. Yerkess, J. Louvet. MARA 01/02 - Experimental validation of the SEURBNUK and SIRIUS containment codes. Proc. 6th Int. Conf. on Structural Mechanics In Reactor Technology, Paper E 3/6, Paris, France: August 1981.
• [2] C. Albertini, et al. The JRC-COVA programme : Final Report. Commission of the European Communities, Report EUR 8705, 1983. Nuclear Science and Technology: 1-182, 1984.
• [3] A. Benuzzi. Comparison of different LMFBR primary containment codes applied to a benchmark problem. Nuclear Engineering and Design, 100: 239-249, 1987.
• [4] Y. Blanchet, P. Obry, J. Louvet. Treatment of fluid-structure interaction with the SIRIUS computer code. Proc. 6th Int. Conf. on Structural Mechanics In Reactor Technology, Paper B 8/8, Paris, France: August 1981.
• [5] C. Bour, M. Sperandio, J. Louvet, C. Rieg. LMFBR's core disruptive accident. Mechanical study of the reactor block. Proc. 10th Int. Conf. on Structural Mechanics In Reactor Technology, Anaheim, USA, Vol. E: 281-287, August 1989.
• [6] H. Bung, F. Casadei, J.P. Halleux, M. Lepareux. PLEXIS-3C: A computer code for fast dynamic problems for structures and fluids. Proc. 10th Int. Conf. on Structural Mechanics In Reactor Technology, Vol. B: 85-90, Anaheim, USA, August 1989.
• [7] I.G. Cameron, B.C. Hankin, A.G.P. Warham, A. Benuzzi, A. Yerkess. The computer code SEURBNUK-2 for fast reactor explosion containment safety studies. Proc. 4th Int. Conf. on Structural Mechanics In Reactor Technology, Paper B 2/1, San Francisco, USA: August 1977.
• [8] Y. Cariou, M. Sperandio, M. Lepareux, K. Christodoulou. LMFBR's whole core accident. Validation of the PLEXUS code by comparison with MARA tests. Proc. 12th Int. Conf. on Structural Mechanics In Reactor Technology, Paper E 7/4, Stuttgart, Germany: August 1993.
• [9] Y. Cariou, J.P. Pirus, C. Ayallet. LMR large accident analysis method. Proc. 14th Int. Conf. on Structural Mechanics In Reactor Technology, Paper P 3/7, 395-402, Lyon, Pi-ance: August 1997.
• [10] Y. Cariou, M. Lepareux, H. Noe. LMR's whole core accident. Validation of the PLEXUS code by comparison with MARS test. Proc. 14th Int. Conf. on Structural Mechanics In Reactor Tecfmology, Paper P 2/6, 339-346, Lyon, France: August 1997.
• [11] F. Casadei, A. Daneri, G. Toselli. Use of PLEXUS as a LMFBR primary containment code for the GONT benchmark problem. Proc. 10th Int. Conf. on Structural Mechanics In Reactor Technology, Paper E 13/1, 299-304, Anaheim, USA: August 1989.
• [12] Y.W. Chang, J. Gvildys, S.H. Fistedis. Analysis of the primary containment response using a hydrodynamic-elastic-plastic computer code. Nuclear Engineering and Design, 27: 155-175, 1974.
• [13] Y.W. Chang. Application of containment codes to LMFBRs in the United States. Nuclear Engineering and Design, 42: 53-67, 1977.
• [14] C. Chavant, A. Hoffmann, P. Verpeaux, J. Dubois. Plexus: A general computer code for explicit Lagrangian computation. Proc. 5th Int. Conf. on Structural Integrity In Reactor Technology, Paper B 2/8, Berlin, Germany, 1979.
• [15] M. Cigarini, A. Daneri, G. Toselli. Applications of ASTARTE-4 code to explosive models with complex internal structure using the rezoning facility. Proc. 7th Int. Conf. on Structural Mechanics In Reactor Technology, Paper B 9/3, Chicago, USA, August 1983.
• [16] M.S. Cowler, S.L. Hancock. Dynamic fluid-structure analysis of shells using the PISCES 2 DELK computer code. Proc. 5th Int. Conf. on Structural Mechanics In Reactor Technology, Paper B 1/6, Berlin, Germany, 1979.
• [17] A. Daneri, G. Toselłi, T. Trombetti, Y. Blanchet, J. Louvet, P. Obry. Influence of the representation models of the stress-strain law on the LMFBR structures in an HCDA. Proc. 5th Int. Conf. on Structural Mechanics In Reactor Technology, Paper E 4/4, Paris, France, August 1981.
• [18] F. David. Etude d'une composition explosive flegmatisée. Applications a la deformation d'une cuve. Proc. Symposium sur les hautes pressions dynamiques, Paris, France, 1978.
• [19] M. Falgayrettes, C. Fiche, P. Granet, P. Hamon, P. Barrau, B. Magnon, J. Jalouneix, M. Nfedelec. Response of a 1/20 scale mock-up of the Superphenix breeder reactor to an HCDA loading simulation. Proc. 7th Int. Conf. on Structural Mechanics In Reactor Technology, Paper E 4/1, 157-166, Chicago, USA, 1983.
• [20] C. Fiche, J. Louvet, B.L. Smith, A. Zucchini. Theoretical experimental study of flexible roof effects in an HCDA's simulation. Proc. 5th Int. Conf. on Structural Mechanics In Reactor Technology, Paper E 4/5, 139-144, Brussels, Belgium, August 1985.
• [21] J.L. Graveleau, P. Louvet. Calculation of fluid-structure interaction for reactor safety with the CASSIOPEE code. Proc. 5th Int. Conf. on Structural Mechanics In Reactor Technology, Paper B 1/7, Berlin, Germany, August 1979.
• [22] A. Hoffmann, M. Lepareux, B. Schwab, H. Bung. Plexus - A general computer program for fast dynamic analysis. Proc. Conference on Structural Analysis and Design on Nuclear Power Plant, Porto Alegre, Brazil, 1984.
• [23] H. Holtbecker. Testing philosophy and simulation techniques. Nuclear Engineering and Design 42: 75-87, 1977.
• [24] N.E. Hoskin, M.J. Lancefield. The COVA programme for the validation of computer codes for fast reactor containment studies. Nuclear Engineering and Design, 46: 17-46, 1978.
• [25] I. E. IdePCik. Memento des pertes de charge. Coefficients de pertes de charge singulićres et de peries de charge par frottement. Collection de la Direction des Etudes et Rechercłie d'EDF, Eyrolles, Paris, France: 362-365, 1986.
• [26] K.C. Kendall, A. Benuzzi. The COVA programme: Validation of the fast reactor containment code SEURBNUK. Nuclear Engineering and Design, 57: 79-105, 1980.
• [27] K.C. Kendall, D.J. Adnams. Experiments to validate structural dynamics code used in fast reactor safety assessment. Science and Technology of Fast Reactor Safety, Vol. 2, British Nuclear Energy Society, London, England, 1986.
• [28] M. Lepareux, B. Schwab, A. Hoffmann, P. Jamet, H. Bung. Un programme general pour Tanalyse dynamique rapide - Cas des tuyauteries. Proc. Colloque Tendances Actuelles en Calcul des Structures, Bastia, Firance, 1985.
• [29] M. Lepareux, B. Schwab, H. Bung. Plexus: A general computer program for the fast dynamic analysis. The case of pipe-circuits. Proc. 5th Int. Conf. on Structural Mechanics In Reactor Technology, Paper FI 2/1, Brussels, Belgium, 1985.
• [30] M. Lepareux, H. Bung, A. Combescure, J. Aguilar. Analysis of a GDA in a LMFBR with a multiphasic and multicomponent behaviour law. Proc. 11th Int. Conf. on Structural Mechanics In Reactor Technology, Paper E 13/1, 371-376, Tokyo, Japan, August 1991.
• [31] M. Lepareux, H. Bung, A. Combescure, J. Aguilar, J.F. Flobert. Analysis of an HCDA in a fast reactor with a multiphase and multicomponent behavior law. Proc. 12th Int. Conf. on Structural Mechanics In Reactor Technology, Paper E 7/2, 197-202, Stuttgart, Germany, August 1993.
• [32] M. Lepareux, J.M. Michelin, D. Thiault. Plexus-R : une extension de Plexus à la robotiąue. CEA report DMT/94-138, 1994.
• [33] J. Louvet, P. Hamon, B.L. Smith, A. Zucchini. MARA 10: an integral model experiment in support of LMFBR containment analysis. Proc. 9th Int. Conf. on Structural Mechanics In Reactor Technology, Vol. E: 331-337, Lausanne, Switzerland, August 1987.
• [34] J. Louvet. Containment response to a core energy release. Main experimental and theorical issues - Future trends. Proc. 10th Int. Conf. on Structural Mechanics In Reactor Technology, Vol. E: 305-310, Anaheim, USA, August 1989.
• [35] NERSA. The Creys-Maluille power plant, Electricité de France. Direction de l’equipement, Region d' equipement Alpes-Lyon, France, 1987.
• [36] M.F. Robbe, M. Lepareux, H. Bung. Plexus - Notice theorique. CEA report DMT/94-490, 1994.
• [37] M.F. Robbe, P. Galon, T. Yuritzinn. Gastem-Plexus: Un logiciel de dynamique rapide pour evaluer Tintegrite des structures en cas d'accident. Proc. 4th Conf. INSTRUC, Courbevoie, France, November 1999.
• [38] M.F. Robbe, Y. Cariou, M. Lepareux, E. Treille. Computation of the MARS test simulating a Hypothetical Core Disruptive Accident in a smali scalę replica of a Fast Breeder Reactor. Proc. Int. Conf. on Numerical Methods in Continuum Mechanics 2000, CD-rom, Liptoysky Jan, Sloyak Republic, September 2000.
• [39] M.F. Robbe, Y. Cariou, E. Treille, M. Lepareux. Comparison of a Core Disruptive Accident simulation with the MARS experimental test. Proc. Int. Conf. on Numerical Methods in Continuum Mechanics 2000, CD-rom, Liptoysky Jan, Sloyak Republic, September 2000.
• [40] M.F. Robbe, N. Vivien, M. Valette, E. Berglas. Use of thermalhydraulic and mechanical linked computations to estimate the mechanical consequences of a steam explosion. Journal of Mechanical Engineering, 52 (2): 65-90, 200 L
• [41] M.F. Robbe, M. Lepareux, E. Treille, Y. Cariou. Numerical simulation of an explosion in a simple scale model of a nuclear reactor. Journal of Computer Assisted Mechanics and Engineering Sciences, 9 (4): 489-517, 2002.
• [42] M.F. Robbe, M. Lepareux. Evaluation of the mechanical consequences of a steam explosion in a nuclear reactor. Bulgarian Journal of Theoretical and Applied Mechanics, 32 (1): 48-84, 2002.
• [43] M.F. Robbe, M. Lepareux, C. Tiollat. Hydrodynamic loads on a PWR primary circuit due to a LOCA. Nuclear Engineering and Design, 211: 189-228, 2002.
• [44] M.F. Robbe, F. Bliard. A porosity method to describe the influence of internal structures on a fluid flow in case of fast dynamics problems. Nuclear Engineering and Design, 215: 217-242, 2002.
• [45] M.F. Robbe, M. Lepareux, Y. Cariou. Numerical interpretation of the MARA 8 experiment simulating a Hypothetical Core Disruptive Accident. Nuclear Engineering and Design, 220: 119-158, 2003.
• [46] M.F. Robbe, M. Lepareux, E. Treille, Y. Cariou. Numerical simulation of a Hypothetical Core Disruptiye Accident in a simple scale model of a nuclear reactor. Nuclear Engineering and Design, 223, (2): 159-196, 2003.
• [47] M.F. Robbe, M. Lepareux. Comparison of the numerical results of Europlexus with the MARS experiment. Proc. llth Int. Conf. On Nuclear Engineering, CD-rom, Tokyo, Japon, Paper 403, April 2003.
• [48] M.F. Robbe, P. Sardain. Comparison of several simplified models and scenarios to simulate a steam explosion in a tank. Journal of Mechanical Engineering, 54 (2): 82-100, 2003.
• [49] M.F. Robbe, S. Potapoy, F. Teffany. Simulation of the depressurisation occuring at the beginning of a LOCA in a 4-loop PWR. Nuclear Engineering and Design, 223: 159-196, 2003.
• [50] M.F. Robbe, S. Potapoy. Modeling of the depressurisation induced by a pipe-rupture in the primary circuit of a nuclear plant. Revue Européenne des Elements Finis 12 (4): 459-485, 2003.
• [51] M.F. Robbe, F. Casadei. Comparison of various models for the simulation of a Core Disruptive Accident in the MARA 10 mock-up. Nuclear Engineering and Design, 232: 301-326, 2004.
• [52] M.F. Robbe, M. Lepareux, E. Seinturie. Results of the simulation of a Core Disruptiye Accident in the MARS mock-up. Proc. 4th Student Conf. of the American Nuclear Society, CD-rom, Madison University, Winsconsin, USA, April 2004,
• [53] J.E.A. Sidoli, K.C. Kendall. The WINCON programme - Validation of the fast reactor primary containment codes. Proc. INE Int. Conf. On Nuclear Containment, Cambridge, England, April 1987. Nuclear Containment Structures, D.G. Walton, Cambridge University Press, 1988.
• [54] B.L. Smith, A. Verkess, J. Adamson. Status of coupled fluid-structure dynamics code SEURBNUK. Proc. 7th Int. Conf. on Structural Mechanics In Reactor Technology, Paper B 9/1, Chicago, USA, August 1983.
• [55] B.L. Smith, C. Fiche, J. Louvet, A. Zucchini. A code comparison exercise based on the LMFBR containment experiment MARA-04. Proc. 5th Int. Conf. on Structural Mechanics In Reactor Technology, Paper E 4/7, 151- 157, Brussels, Belgium, August 1985.
• [56] B.L. Smith, A. Verkess, Y. Washby. The computer code SEURBNUK-EURDYN: First release version. Proc. 9th Int. Conf. on Structural Mechanics In Reactor Technology, Lausanne, Switzerland, August 1987.
• [57] M. Stieyenart, P. Bouffioux, M. Eglème, J.P. Fabry, H. Lamotte. Analysis of LMFBR explosion model experiments by means of the Surboum-II code. Proc. 3rd Int. Conf. on Structural Mechanics In Reactor Technology, Paper E 3/5, London, England, August 1975.
• [58] E. Studer, P. Galon. Hydrogen combustion loads - Plexus calculations. Nuclear Engineering and Design, 174: 119-134, 1997.
• [59] H.U. Wenger, B.L. Smith. On the origin of the discrepancies between theory and experiment in the GOYA series. Proc. 9th Int. Conf. on Structural Mechanics In Reactor Technology, Vol. E: 339-344, Lausanne, Switzerland, 1987.
• [60] P.H. West, N.E. Hoskin. APRICOT - Phase 3. Suggested simple test problems for examination of thin shell modelling and fluid structure coupling. Aldermaston report AWRE/44/92/16, 1980.