Modeling of the depressurisation induced by a pipe rupture in the primary circuit of a nuclear plant

Revue Europeenne des Elements

Volumn 12, Issue 4, 2003, Pages 459-485

  Robbe, Marie France ^a   Potapov, Serguei ^b  

^a CEA SACLAY   (France)

^b EDF R AND D   (France)

Author keywords

Fast dynamics; Hydraulic; Nuclear reactor; Numerical simulation

Indexed keywords

ACCIDENTS; COMPUTER SIMULATION; HYDRAULICS; LOSS OF COOLANT ACCIDENTS; NUCLEAR REACTORS; PRESSURIZED WATER REACTORS;

FAST DYNAMICS; NUCLEAR PLANT; PIPE RUPTURE; PRESSURISED WATER REACTOR; PRIMARY CIRCUITS; SAFETY ANALYSIS;

NUMERICAL MODELS;

EID: 0037640180     PISSN: 12506559     EISSN: None     Source Type: Journal    
DOI: 10.3166/reef.12.459-485     Document Type: Article

References (49)

1. Bliard F., Lepareux M., Programme PLEXUS, Modélisation d'un composant de type pompe,CEA report DMT/95-269, 1995.
2. Bung H., Casadei F., Halleux J.P., Lepareux M., " PLEXIS-3C: A computer code for fast dynamic problems for structures and fluids" , Proceedings of the tenth International Conference on Structural Mechanics In Reactor Technology SMIRT 10, Vol. B, Anaheim,USA, August 1989, pp. 85-90.
3. Caumette P., Chouard P., Martin A., " Study of pipe rupture dynamics: Aquitaine II program" , Proceedings of the sixth International Conference on Structural Mechanics In Reactor Technology SMIRT 6, paper F 8/4, Paris, France, August 1981.
4. Cauquelin C., Caumette P., Garcia J.L., Sermet E., " Experimental studies of PWR primary piping under LOCA conditions" , Proceedings of the fifth International Conference on Structural Mechanics In Reactor Technology SMIRT 5, paper F 6/1, Berlin, Germany, August 1979.
5. Chavant C., Hoffmann A., Verpeaux P., Dubois J., " Plexus: A general computer code for explicit lagrangian computation" , Proceedings of the fifth International Conference on Structural Mechanics In Reactor Technology SMIRT 5, paper B 2/8, Berlin, Germany, August 1979.
6. Couilleaux J., Lazare-Chopard G., Fouettement de tuyauteries RIC des paliers de 900 MWE, CEA report DEMT/SMTS/LAMS/84-26, 1984.
7. Dupuy A.P., Martin A., Thomas J.P., Garcia J.L., Caumette P., Chouard P., " Mechanical effects of breaks on PWR primary pipings, Analytical interpretation of tests" , Proceedings of the seventh International Conference on Structural Mechanics In Reactor Technology SMIRT 7, paper F 1/4, Chicago, USA, August 1983.
8. Galon P., Lepareux M., Documentation théorique, Modélisation des tuyauteries dans EUROPLEXUS, CEA report SEMT/DYN/RT/01-021, 2001.
9. Garcia J.L., Caumette P., Huet J.L., " Studies of pipe whip and impact" , Proceedings of the sixth International Conference on Structural Mechanics In Reactor Technology SMIRT 6, paper F 8/6, Paris, France, August 1981.
10. Garcia J.L., Martin A., Chouard P., " A simplified methodology for calculations of pipe impacts: comparison with tests" , Proceedings of the ASME conference Pressure Vessel and Piping, Vol. 2, Phoenix, USA, 1982.
11. Gibert R.J., Vibrations des structures. Interactions avec les fluides. Sources d'excitation aléatoires, Collection de la Direction des Etudes et Recherches d'Electricité De France,Eyrolles, Paris, France, 1988, pp. 268-281.
12. Gruen G.E., Wham prediction of semiscale test results, USA Atomic Energy Commission Idaho Operations office, Contract no. AT(10-1)-123, 1970.
13. Guilbaud D., Gantenbein F., Gibert R.J., " A substructure method to compute 3D fluidstructure interaction during blowdown" , Proceedings of the seventh International Conference on Structural Mechanics In Reactor Technology SMIRT 7, paper F 8/4, Chicago, USA, August 1983.
14. Guilbaud D., Gibert R.J., " Calculation of a HDR blowdown test using a substructure method" , Proceedings of the seventh International Conference on Structural Mechanics In Reactor Technology SMIRT 7, paper B 10/1, Chicago, USA, August 1983.
15. Guilbaud D., " Dynamic response of PWR vessel during a blowdown" , Proceedings of the ninth International Conference on Structural Mechanics In Reactor Technology SMIRT 9, Vol. F, Lausanne, Switzerland, August 1987.
16. Haar L., Gallagher J.S., Kell G.S., NBS/NRC steam tables, National Standard Reference Data System, 1984.
17. HDR Sicherheltsprogramm, Untersuchlungen von RDB Einbauten bei Bruch einer Reaktorühlmitteleitung, Quick look report, Vol. 29/2, Technischer Fachbericht, 1980, pp. 16-80.
18. Hoffmann A., Lepareux M., Schwab B., Bung H., " Plexus: A general computer program for fast dynamic analysis" , Proceedings of the Conference on Structural Analysis and Design on Nuclear Power Plant, Porto Alegre, Brazil, 1984.
19. Idel'Cik I.E., Memento des pertes de charge, Coefficients de pertes de charge singulières et de pertes de charge par frottement, Collection de la Direction des Etudes et Recherche d'Electricité De France, Eyrolles, Paris, France, 1986.
20. Jeanpierre F., Gibert R.J., Hoffmann A., Livolant M., " Description of a general method to compute the fluid-structure interaction" , Proceedings of the fifth International Conference on Structural Mechanics In Reactor Technology SMIRT 5, paper B 4/1, Berlin, Germany, August 1979.
21. Lepareux M., 1974., Rupture de la tuyauterie primaire dans Priam, Etude de la propagation de la dépressurisation dans la cuve pendant les premières millisecondes par le programme Vibraphone, CEA report EMT/74-179.
22. Lepareux M., Dépressurisation brusque, Comparaison des résultats du calcul de propagation (programme Vibraphone) avec une expérience, CEA report EMT/74-260, 1974.
23. Lepareux M., Système CEASEMT, Programme Vibraphone, CEA report EMT/75-40, 1975.
24. Lepareux M., Schwab B., Bung H., " Plexus: A general computer program for the fast dynamic analysis, The case of pipe-circuits" , Proceedings of the eighth International Conference on Structural Mechanics In Reactor Technology SMIRT 8, paper F1 2/1, Brussels, Belgium, August 1985.
25. Lepareux M., Schwab B., Hoffmann A., Jamet P., Bung H., " Un programme général pour l'analyse dynamique rapide - Cas des tuyauteries" , Proceedings of the Colloque Tendances Actuelles en Calcul des Structures, Bastia, France, 1985.
26. Lepareux M., Combescure A., Makil H., " Hydromechanical analysis of a primary pipe (1D) coupled to a reactor vessel (3D) during a depressurization" , Proceedings of the eleventh International Conference on Structural Mechanics In Reactor Technology SMIRT 11, paper F 5/4, Tokyo, Japan, August 1991.
27. Lepareux M., Michelin J.M., Thiault D., Plexus-R: une extension de Plexus à la robotique, CEA report DMT/94-138, 1994.
28. Lepareux M., Programme PLEXUS, Matériau eau, Modèle homogène équilibré, CEA report DMT/94-398, 1994.
29. Lepareux M., Programme PLEXUS: les modèles de débit critique, CEA report DMT/97-29, 1997.
30. Libmann J., Eléments de sûreté nucléaire, IPSN, Les éditions de la physique, France, 1996.
31. Millard A., Jamet P, Lieutenant J.L., Schwab B., Goetsch D., " Whip analysis of guide-pipes of instrumentation below PWR vessels" , Proceedings of the eighth International Conference on Structural Mechanics In Reactor Technology SMIRT 8, paper F1 4/7, Brussels, Belgium, August 1985.
32. Moody F.J., " Maximum flow rate of a single component two-phase mixture" , Journal of heat transfer, February 1965.
33. Papon P., Leblond J., Thermodynamique des états de la matière, Editeurs des Sciences et des Arts, Hermann, Paris, France, 1990.
34. Potapov S., Robbe M.F., Téphany F., " Hydrodynamic consequences of a LOCA in a 4-loop PWR" , Proceedings of the European Congress on Computational Methods in Applied Sciences and Engineering ECCOMAS, CD-rom, Barcelona, Spain, September 2000.
35. Robbe M.F., Lepareux M., Bung H., PLEXUS, Notice théorique, CEA report DMT/94-490, 1994.
36. Robbe M.F., Lepareux M., Programme PLEXUS, Matériau eau, Modèle homogène non équilibré, CEA report DMT/96-142, 1996.
37. Robbe M.F., Galon P., Yuritzinn T., " Castem-Plexus: un logiciel de dynamique rapide pour évaluer l'intégrité des structures en cas d'accident" , Proceedings of the fourth Conference INSTRUC, Courbevoie, France, November 1999.
38. Robbe M.F., Potapov S., " A pipe-model to assess the hydrodynamic effects of a blowdown in a 4-loop PWR" , Proceedings of the eighth International Conference On Nuclear Engineering ICONE 8, paper 8186, CD-rom, Baltimore, USA, April 2000.
39. 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" , Journal of Mechanical Engineering, Vol. 52, 2001, pp. 65-90.
40. Robbe M.F., Potapov S., Téphany F., " Modeling of the hydraulic flows in a 4-loop PWR with a pipe-geometry" , Proceedings of the ninth International Cconference On Nuclear Engineering ICONE 9, paper 9864, CD-rom, Nice, France, April 2001.
41. Robbe M.F., Potapov S., Téphany F., " Estimation of the hydrodynamic effects of a LOCA in a 4-loop PWR" , Proceedings of the ninth International Cconference On Nuclear Engineering ICONE 9, paper 9682, CD-rom, Nice, France, April 2001.
42. Robbe M.F., Potapov S., Téphany F., " Simulation of the blowdown induced by a LOCA in a 4-loop PWR" , Proceedings of the 1st ANS/HPS student conference, CD-rom, Texas A& M University, College Station, USA, March 2001.
43. Robbe M.F., Lepareux M., Trollat C., " Hydrodynamic loads on a PWR primary circuit due to a LOCA" , Nuclear Engineering and Design, Vol. 211, No 2-3, 2002, pp. 189-228.
44. Robbe M.F., Lepareux M., " Evaluation of the mechanical consequences of a steam explosion in a nuclear reactor" , Bulgarian Journal of Theoretical and Applied Mechanics, Vol. 32, No 1, 2002, pp. 48-84.
45. Robbe M.F., Lepareux M., Treille E., Cariou Y., " Numerical simulation of an explosion in a simple scale model of a nuclear reactor" , Journal of Computer Assisted Mechanics and Engineering Sciences, Vol. 9, No 4, 2002, pp. 489-517.
46. 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" , Nuclear Engineering and Design, Vol. 215, 2002, p. 217-242.
47. Robbe M.F., Lepareux M., Cariou Y., " Numerical interpretation of the MARA 8 experiment simulating a Hypothetical Core Disruptive Accident" , Nuclear Engineering and Design, in press, 2002.
48. Schwab B., Lepareux M., Combescure A., Makil H., " Hydromechanical analysis of a primary pipe (1D) coupled to a reactor vessel (3D) during a depressurization" , Proceedings of the tenth International Conference on Structural Mechanics In Reactor Technology SMIRT 10, paper T 6/1, Anaheim, USA, August 1989.
49. Struder E., Galon P., " Hydrogen combustion loads Plexus calculations" , Nuclear Engineering and Design, Vol. 174, 1997, pp. 119-134.