Simulation of the depressurisation occuring at the beginning of a LOCA in a 4-loop PWR

Nuclear Engineering and Design

Volumn 224, Issue 1, 2003, Pages 33-63

  Robbe, Marie France ^a   Potapov, S ^b   Tephany F ^b  

^a CEA SACLAY   (France)

^b EDF R AND D   (France)

Author keywords

[No Author keywords available]

Indexed keywords

LOSS OF COOLANT ACCIDENTS; NUMERICAL METHODS; PRESSURIZED WATER REACTORS;

DEPRESSURIZATION;

NUCLEAR ENGINEERING;

EID: 0038315653     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(03)00076-1     Document Type: Article

References (44)

1. 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 (SMIRT 10), vol. B, Anaheim, USA, pp. 85-90.
2. Cauquelin, C., Caumette, P., Garcia, J.L., Sermet, E., 1979. Experimental studies of PWR primary piping under LOCA conditions. In: Proceedings of the 5th International Conference on Structural Mechanics in Reactor Technology (SMIRT 5), Paper F 6/1, Berlin, Germany.
3. Caumette, P., Chouard, P., Martin, A., 1981. Study of pipe rupture dynamics: Aquitaine II program. In: Proceedings of the 6th International Conference on Structural Mechanics in Reactor Technology (SMIRT 6), Paper F 8/4, Paris, France.
4. Chavant, C., Hoffmann, A., Verpeaux, P., Dubois, J., 1979. Plexus: a general computer code for explicit lagrangian computation. In: Proceedings of the 5th International Conference on Structural Mechanics in Reactor Technology (SMIRT 5), Paper B 2/8, Berlin, Germany.
5. Couilleaux, J., Lazare-Chopard, G., 1984. Fouettement de tuyauteries RIC des paliers de 900 MWE. CEA report DEMT/SMTS/LAMS/84-26.
6. Dupuy, A.P., Martin, A., Thomas, J.P., Garcia, J.L., Caumette, P., Chouard, P., 1983. Mechanical effects of breaks on PWR primary pipings. Analytical interpretation of tests. In: Proceedings of the 7th International Conference on Structural Mechanics in Reactor Technology (SMIRT 7), Paper F 1/4, Chicago, USA.
7. Garcia, J.L., Caumette, P., Huet, J.L., 1981. Studies of pipe whip and impact. In: Proceedings of the 6th International Conference on Structural Mechanics in Reactor Technology (SMIRT 6), Paper F 8/6, Paris, France.
8. Garcia, J.L., Martin, A., Chouard, P., 1982. A simplified methodology for calculations of pipe impacts: comparison with tests. In: Proceedings of ASME Conference on Pressure Vessel and Piping, vol. 2, Phoenix, USA.
9. Gibert, R.J., 1988. 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, pp. 268-281.
10. Gruen, G.E., 1970. Wham prediction of semiscale test results. USA Atomic Energy Commission Idaho Operations office, Contract No. AT(10-1)-123.
11. Guilbaud, D., 1987. Dynamic response of PWR vessel during a blowdown. In: Proceedings of the 9th International Conference on Structural Mechanics in Reactor Technology (SMIRT 9), vol. F, Lausanne, Switzerland.
12. Guilbaud, D., Gibert, R.J., 1983. Calculation of a HDR blowdown test using a substructure method. In: Proceedings of the 7th International Conference on Structural Mechanics in Reactor Technology (SMIRT 7), Paper B 10/1, Chicago, USA.
13. Guilbaud, D., Gantenbein, F., Gibert, R.J., 1983. A substructure method to compute 3D fluid-structure interaction during blowdown. In: Proceedings of the 7th International Conference on Structural Mechanics in Reactor Technology (SMIRT 7), Paper F 8/4, Chicago, USA.
14. Haar, L., Gallagher, J.S., Kell, G.S., 1984. NBS/NRC steam tables. National Standard Reference Data System.
15. HDR Sicherheltsprogramm, 1980. Untersuchlungen von RDB Einbauten bei Bruch einer Reaktorühlmitteleitung. Quick look report, V 29/2, Technischer Fachbericht, pp. 16-80.
16. 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.
17. Idel'Cik, I.E., 1986. 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.
18. Jeanpierre, F., Gibert, R.J., Hoffmann, A., Livolant, M., 1979. Description of a general method to compute the fluid-structure interaction. In: Proceedings of the 5th International Conference on Structural Mechanics in Reactor Technology (SMIRT 5), Paper B 4/1, Berlin, Germany.
19. Lepareux, M., 1974a. 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.
20. Lepareux, M., 1974b. Dépressurisation brusque - comparaison des résultats du calcul de propagation (programme Vibraphone) avec une expérience. CEA report EMT/74-260.
21. Lepareux, M., 1975. Système CEASEMT - Programme Vibraphone. CEA report EMT/75-40.
22. Lepareux, M., Schwab, B., Bung, H., 1985a. Plexus: a general computer program for the fast dynamic analysis. The case of pipe-circuits. In: Proceedings of the 8th International Conference on Structural Mechanics in Reactor Technology (SMIRT 8), Paper F1 2/1, Brussels, Belgium.
23. Lepareux, M., Schwab, B., Hoffmann, A., Jamet, P., Bung, H., 1985b. Un programme général pour l'analyse dynamique rapide - cas des tuyauteries. In: Proc. Colloque Tendances Actuelles en Calcul des Structures, Bastia, France.
24. Lepareux, M., Combescure, A., Makil, H., 1991. Hydromechanical analysis of a primary pipe (1D) coupled to a reactor vessel (3D) during a depressurization. In: Proceedings of the 11th International Conference on Structural Mechanics in Reactor Technology (SMIRT 11), Paper F 5/4, Tokyo, Japan.
25. Lepareux, M., Michelin, J.M., Thiault, D., 1994. Plexus-R: une extension de plexus à la robotique. CEA report DMT/94-138.
26. Libmann, J., 1996. Eléments de sûreté nucléaire, IPSN, Les éditions de la physique, France.
27. Millard, A., Jamet, P, Lieutenant, J.L., Schwab, B., Goetsch D., 1985. Whip analysis of guide-pipes of instrumentation below PWR vessels. In: Proceedings of the 8th International Conference on Structural Mechanics in Reactor Technology (SMIRT 8), Paper F1 4/7, Brussels, Belgium.
28. Moody, F.J., 1965. Maximum flow rate of a single component two-phase mixture. J. Heat Transfer.
29. Papon, P., Leblond, J., 1990. Thermodynamique des états de la matière. Editeurs des Sciences et des Arts, Hermann, Paris, France.
30. Potapov, S., Robbe, M.F., Téphany, F., 2000. Hydrodynamic consequences of a LOCA in a 4-loop PWR. In: Proceedings of European Congress on Computational Methods in Applied Sciences and Engineering ECCOMAS, CD-ROM, Barcelona, Spain.
31. 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. Design. 215:2002;217-242.
32. Robbe, M.F., Potapov, S., 2000. A pipe-model to assess the hydrodynamic effects of a blowdown in a 4-loop PWR. In: Proceedings of the 8th International Conference on Nuclear Engineering (ICONE 8), Paper 8186, CD-ROM, Baltimore, USA.
33. Robbe, M.F., Lepareux, M., Bung, H., 1994. PLEXUS: notice théorique. CEA report DMT/94-490.
34. 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 4th Conference INSTRUC, Courbevoie, France.
35. Robbe, M.F., Potapov, S., Téphany, F., 2001a. Modeling of the hydraulic flows in a 4-loop PWR with a pipe-geometry. In: Proceedings of the 8th International Conference on Nuclear Engineering (ICONE 9), Paper 9864, CD-ROM, Nice, France.
36. Robbe, M.F., Potapov, S., Téphany, F., 2001b. Estimation of the hydrodynamic effects of a LOCA in a 4-loop PWR. In: Proceedings of the 9th International Conference on Nuclear Engineering (ICONE 9), Paper 9682, CD-ROM, Nice, France.
37. Robbe, M.F., Potapov, S., Téphany, F., 2001c. Simulation of the blowdown induced by a LOCA in a 4-loop PWR. In: Proceedings of the 1st ANS/HPS student conference, CD-ROM, Texas A&M University, College Station, USA.
38. 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(2):2001d;65-90.
39. Robbe M.F., Lepareux M., Trollat C., Hydrodynamic loads on a PWR primary circuit due to a LOCA. Nucl. Eng. Design. 211(2/3):2002a;189-228.
40. Robbe M.F., Lepareux M., Evaluation of the mechanical consequences of a steam explosion in a nuclear reactor. Bulg. J. Theor. Appl. Mech. 32(1):2002b;48-84.
41. 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(4):2002c;489-517.
42. Robbe M.F., Lepareux M., Cariou Y., Numerical interpretation of the MARA 8 experiment simulating a Hypothetical Core Disruptive Accident. Nucl. Eng. Design. 220:2003;119-158.
43. Schwab, B., Lepareux, M., Combescure, A., Makil, H., 1989. Hydromechanical analysis of a primary pipe (1D) coupled to a reactor vessel (3D) during a depressurization. In: Proceedings of the 10th International Conference on Structural Mechanics in Reactor Technology (SMIRT 10), Paper T 6/1, Anaheim, USA.
44. Struder E., Galon P., Hydrogen combustion loads Plexus calculations. Nucl. Eng. Design. 174:1997;119-134.