-
1
-
-
0019703364
-
MARA 01/02-experimental validation of the SEURBNUK and SIRIUS containment codes
-
Section E3/6, Paris, France
-
Acker, D., Benuzzi, A., Yerkess, A., Louvet, J., 1981. MARA 01/02-Experimental validation of the SEURBNUK and SIRIUS containment codes. Proceedings of the Sixth International Conference on Structural Mechanics in Reactor Technology. Section E3/6, Paris, France.
-
(1981)
Proceedings of the Sixth International Conference on Structural Mechanics in Reactor Technology
-
-
Acker, D.1
Benuzzi, A.2
Yerkess, A.3
Louvet, J.4
-
2
-
-
0002122925
-
The JRC-COVA programme: Final Report
-
Commission of the European Communities. Report EUR 8705
-
Albertini, C., et al. 1984. The JRC-COVA programme: Final Report. Commission of the European Communities. Report EUR 8705. Nuclear Science and Technology 1-182.
-
(1984)
Nuclear Science and Technology
, pp. 1-182
-
-
Albertini, C.1
-
3
-
-
0023218675
-
Comparison of different LMFBR primary containment codes applied to a benchmark problem
-
Benuzzi A. Comparison of different LMFBR primary containment codes applied to a benchmark problem. Nuclear Engineering and Design. 100:1987;239-249.
-
(1987)
Nuclear Engineering and Design
, vol.100
, pp. 239-249
-
-
Benuzzi, A.1
-
4
-
-
0019654657
-
Treatment of fluid-structure interaction with the SIRIUS computer code
-
Section B8/8, Paris, France
-
Blanchet, Y., Obry, P., Louvet, J., 1981. Treatment of fluid-structure interaction with the SIRIUS computer code. Proceedings of the Sixth International Conference on Structural Mechanics In Reactor Technology. Section B8/8, Paris, France.
-
(1981)
Proceedings of the Sixth International Conference on Structural Mechanics In Reactor Technology
-
-
Blanchet, Y.1
Obry, P.2
Louvet, J.3
-
5
-
-
0002848947
-
LMFBR's core disruptive accident. Mechanical study of the reactor block
-
Anaheim, USA
-
Bour, C., Spérandio, M., Louvet, J., Rieg, C., 1989. LMFBR's core disruptive accident. Mechanical study of the reactor block. Proceedings of the Tenth International Conference on Structural Mechanics in Reactor Technology. Vol. E, Anaheim, USA, pp. 281-287.
-
(1989)
Proceedings of the Tenth International Conference on Structural Mechanics in Reactor Technology
, vol.E
, pp. 281-287
-
-
Bour, C.1
Spérandio, M.2
Louvet, J.3
Rieg, C.4
-
6
-
-
0002190598
-
LMFBR's whole core accident. Validation of the PLEXUS code by comparison with MARA tests
-
Section E7/4, Stuttgart, Germany
-
Cariou, Y., Spérandio, M., Lepareux, M., Christodoulou, K., 1993. LMFBR's whole core accident. Validation of the PLEXUS code by comparison with MARA tests. Proceedings of the Twelveth International Conference on Structural Mechanics in Reactor Technology. Section E7/4, Stuttgart, Germany.
-
(1993)
Proceedings of the Twelveth International Conference on Structural Mechanics in Reactor Technology
-
-
Cariou, Y.1
Spérandio, M.2
Lepareux, M.3
Christodoulou, K.4
-
7
-
-
0002444065
-
LMR large accident analysis method
-
Section P3/7, Lyon, France
-
Cariou, Y., Pirus, J.P., Avallet, C., 1997. LMR large accident analysis method, Proceedings of the 14th International Conference on Structural Mechanics in Reactor Technology. Section P3/7, Lyon, France, pp. 395-402.
-
(1997)
Proceedings of the 14th International Conference on Structural Mechanics in Reactor Technology
, pp. 395-402
-
-
Cariou, Y.1
Pirus, J.P.2
Avallet, C.3
-
8
-
-
0002890857
-
Use of PLEXUS as a LMFBR primary containment code for the CONT benchmark problem
-
Section E13/1, Anaheim, USA
-
Casadei, F., Daneri, A., Toselli, G., 1989. Use of PLEXUS as a LMFBR primary containment code for the CONT benchmark problem. Proceedings of the Tenth International Conference on Structural Mechanics in Reactor Technology. Section E13/1, Anaheim, USA, pp. 299-304.
-
(1989)
Proceedings of the Tenth International Conference on Structural Mechanics in Reactor Technology
, pp. 299-304
-
-
Casadei, F.1
Daneri, A.2
Toselli, G.3
-
9
-
-
85095888213
-
Plexus: A general computer code for explicit Lagrangian computation
-
Section B2/8. Berlin, Germany
-
Chavant, C., Hoffmann, A., Verpeaux, P., Dubois, J., 1979. Plexus: a general computer code for explicit Lagrangian computation. Proceedings of the Fifth International Conference on Structural Integrity in Reactor Technology. Section B2/8. Berlin, Germany.
-
(1979)
Proceedings of the Fifth International Conference on Structural Integrity in Reactor Technology
-
-
Chavant, C.1
Hoffmann, A.2
Verpeaux, P.3
Dubois, J.4
-
11
-
-
0010666013
-
Etude d'une composition explosive flegmatisée. Applications à la déformation d'une cuve
-
Paris, France
-
David, F., 1978. Etude d'une composition explosive flegmatisée. Applications à la déformation d'une cuve. Proceedings of the Symposium sur les hautes pressions dynamiques. Paris, France.
-
(1978)
Proceedings of the Symposium Sur Les Hautes Pressions Dynamiques
-
-
David, F.1
-
12
-
-
0002568851
-
Theoretical experimental study of flexible roof effects in an HCDA's simulation
-
Section E4/5. Brussels, Belgium
-
Fiche, C., Louvet, J., Smith, B.L., Zucchini, A., 1985. Theoretical experimental study of flexible roof effects in an HCDA's simulation. Proceedings of the Eighth International Conference on Structural Integrity in Reactor Technology. Section E4/5. Brussels, Belgium, pp. 139-144.
-
(1985)
Proceedings of the Eighth International Conference on Structural Integrity in Reactor Technology
, pp. 139-144
-
-
Fiche, C.1
Louvet, J.2
Smith, B.L.3
Zucchini, A.4
-
13
-
-
0003229253
-
Plexus - A general computer program for fast dynamic analysis
-
Porto Alegre, Brazil
-
Hoffmann, A., Lepareux, M., Schwab, B., Bung, H., 1984. 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)
Proceedings of the Conference on Structural Analysis and Design on Nuclear Power Plant
-
-
Hoffmann, A.1
Lepareux, M.2
Schwab, B.3
Bung, H.4
-
14
-
-
0017503156
-
Testing philosophy and simulation techniques
-
Holtbecker H. Testing philosophy and simulation techniques. Nuclear Engineering and Design. 42:1977;75-87.
-
(1977)
Nuclear Engineering and Design
, vol.42
, pp. 75-87
-
-
Holtbecker, H.1
-
15
-
-
0017946599
-
The COVA programme for the validation of computer codes for fast reactor containment studies
-
Hoskin N.E., Lancefield M.J. The COVA programme for the validation of computer codes for fast reactor containment studies. Nuclear Engineering and Design. 46:1978;17-46.
-
(1978)
Nuclear Engineering and Design
, vol.46
, pp. 17-46
-
-
Hoskin, N.E.1
Lancefield, M.J.2
-
16
-
-
0018452582
-
The COVA programme: Validation of the fast reactor containment code SEURBNUK
-
Kendall K.C., Benuzzi A. The COVA programme: validation of the fast reactor containment code SEURBNUK. Nuclear Engineering and Design. 57:1980;79-105.
-
(1980)
Nuclear Engineering and Design
, vol.57
, pp. 79-105
-
-
Kendall, K.C.1
Benuzzi, A.2
-
17
-
-
0022951969
-
Experiments to validate structural dynamics code used in fast reactor safety assessment
-
London, England: British Nuclear Energy Society
-
Kendall K.C., Adnams D.J. Experiments to validate structural dynamics code used in fast reactor safety assessment. Science and Technology of Fast Reactor Safety. 2:1986;British Nuclear Energy Society, London, England.
-
(1986)
Science and Technology of Fast Reactor Safety
, vol.2
-
-
Kendall, K.C.1
Adnams, D.J.2
-
18
-
-
0003296389
-
Un programme général pour l'analyse dynamique rapide-Cas des tuyauteries
-
Bastia, France
-
Lepareux, M., Schwab, B., Hoffmann, A., Jamet, P., Bung, H., 1985. Un programme général pour l'analyse dynamique rapide-Cas des tuyauteries. Proceedings of the Colloque Tendances Actuelles en Calcul des Structures. Bastia, France.
-
(1985)
Proceedings of the Colloque Tendances Actuelles en Calcul des Structures
-
-
Lepareux, M.1
Schwab, B.2
Hoffmann, A.3
Jamet, P.4
Bung, H.5
-
19
-
-
0022240250
-
Plexus: A general computer program for the fast dynamic analysis - The case of pipe-circuits
-
Section F1 2/1. Brussels, Belgium
-
Lepareux, M., Schwab, B., Bung, H., 1985. Plexus: a general computer program for the fast dynamic analysis - the case of pipe-circuits. Proceedings of the 8th International Conference on Structural Mechanics in Reactor Integrity. Section F1 2/1. Brussels, Belgium.
-
(1985)
Proceedings of the 8th International Conference on Structural Mechanics in Reactor Integrity
-
-
Lepareux, M.1
Schwab, B.2
Bung, H.3
-
20
-
-
0002240972
-
Analysis of a CDA in a LMFBR with a multiphasic and multicomponent behaviour law
-
Section E13/1. Tokyo, Japan
-
Lepareux, M., Bung, H., Combescure, A., Aguilar, J., 1991. Analysis of a CDA in a LMFBR with a multiphasic and multicomponent behaviour law. Proceedings of the 11th International Conference on Structural Mechanics in Reactor Integrity. Section E13/1. Tokyo, Japan, pp. 371-376.
-
(1991)
Proceedings of the 11th International Conference on Structural Mechanics in Reactor Integrity
, pp. 371-376
-
-
Lepareux, M.1
Bung, H.2
Combescure, A.3
Aguilar, J.4
-
21
-
-
0002091932
-
Analysis of an HCDA in a fast reactor with a multiphase and multicomponent behavior law
-
Section E7/2. Stuttgart, Germany
-
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. Proceedings of the 12th International Conference on Structural Mechanics in Reactor Integrity. Section E7/2. Stuttgart, Germany, pp. 197-202.
-
(1993)
Proceedings of the 12th International Conference on Structural Mechanics in Reactor Integrity
, pp. 197-202
-
-
Lepareux, M.1
Bung, H.2
Combescure, A.3
Aguilar, J.4
Flobert, J.F.5
-
23
-
-
0001774284
-
MARA 10: An integral model experiment in support of LMFBR containment analysis
-
Lausanne, Switzerland
-
Louvet, J., Hamon, P., Smith, B.L., Zucchini, A., 1987. MARA 10: an integral model experiment in support of LMFBR containment analysis. Proceedings of the Ninth International Conference on Structural Mechanics in Reactor Integrity. Vol. E. Lausanne, Switzerland, pp. 331-337.
-
(1987)
Proceedings of the Ninth International Conference on Structural Mechanics in Reactor Integrity
, vol.E
, pp. 331-337
-
-
Louvet, J.1
Hamon, P.2
Smith, B.L.3
Zucchini, A.4
-
26
-
-
0037640174
-
Castem-plexus: Un logiciel de dynamique rapide pour évaluer l'intégrité des structures en cas d'accident
-
France
-
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. Proceedings of the Fourth Conference INSTRUC. Courbevoie, France.
-
(1999)
Proceedings of the Fourth Conference INSTRUC. Courbevoie
-
-
Robbe, M.F.1
Galon, P.2
Yuritzinn, T.3
-
27
-
-
0002172211
-
Use of thermalhydraulic and mechanical linked computations to estimate the mechanical consequences of a steam explosion
-
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. Slovak Journal of Mechanical Engineering. 2:2001;65-90.
-
(2001)
Slovak Journal of Mechanical Engineering
, vol.2
, pp. 65-90
-
-
Robbe, M.F.1
Vivien, N.2
Valette, M.3
Berglas, E.4
-
28
-
-
0036398139
-
Numerical simulation of an explosion in a simple scale model of a nuclear reactor
-
In press
-
Robbe, M.F., Lepareux, M., Treille, E., Cariou, Y., 2002a. Numerical simulation of an explosion in a simple scale model of a nuclear reactor. Computer Assisted Mechanics and Engineering Sciences, In press.
-
(2002)
Computer Assisted Mechanics and Engineering Sciences
-
-
Robbe, M.F.1
Lepareux, M.2
Treille, E.3
Cariou, Y.4
-
29
-
-
0003335563
-
Evaluation of the mechanical consequences of a steam explosion in a nuclear reactor
-
Robbe, M.F., Lepareux, M., 2002b. Evaluation of the mechanical consequences of a steam explosion in a nuclear reactor. Bulgarian Journal of Theoretical and Applied Mechanics, 32, No 1.
-
(2002)
Bulgarian Journal of Theoretical and Applied Mechanics
, vol.32
, Issue.1
-
-
Robbe, M.F.1
Lepareux, M.2
-
30
-
-
0036467965
-
Hydrodynamic loads on a PWR primary circuit due to a LOCA
-
Robbe M.F., Lepareux M., Trollat C. Hydrodynamic loads on a PWR primary circuit due to a LOCA. Nuclear Engineering and Design. 211:(Nos 2-3):2002c;189-228.
-
(2002)
Nuclear Engineering and Design
, vol.211
, Issue.2-3
, pp. 189-228
-
-
Robbe, M.F.1
Lepareux, M.2
Trollat, C.3
-
31
-
-
0036390601
-
Assessment of the hydraulic flows in the MARA 8 test-facility simulating a HCDA
-
Paper 10687, CD-ROM, Arlington, USA
-
Robbe, M.F., Lepareux, M., 2002d. Assessment of the hydraulic flows in the MARA 8 test-facility simulating a HCDA. Proceedings of the Tenth International Conference on Nuclear Engineering. Paper 10687, CD-ROM, Arlington, USA.
-
(2002)
Proceedings of the Tenth International Conference on Nuclear Engineering
-
-
Robbe, M.F.1
Lepareux, M.2
-
32
-
-
0036393316
-
Assessment of the mechanical effects of a HCDA in a simple scale model of a LMFBR
-
Paper 10689, CD-ROM, Arlington, USA
-
Robbe, M.F., Lepareux, M., 2002e. Assessment of the mechanical effects of a HCDA in a simple scale model of a LMFBR. Proceedings of the Tenth International Conference On Nuclear Engineering. Paper 10689, CD-ROM, Arlington, USA.
-
(2002)
Proceedings of the Tenth International Conference On Nuclear Engineering
-
-
Robbe, M.F.1
Lepareux, M.2
-
33
-
-
0036390974
-
Comparison of a HCDA numerical simulation with the results of the MARA8 test
-
Article 10690, CD-ROM, Arlington, USA
-
Robbe, M.F., Lepareux, M., 2002f. Comparison of a HCDA numerical simulation with the results of the MARA8 test. Proceedings of the Tenth International Conference on Nuclear Engineering. Article 10690, CD-ROM, Arlington, USA.
-
(2002)
Proceedings of the Tenth International Conference on Nuclear Engineering
-
-
Robbe, M.F.1
Lepareux, M.2
-
34
-
-
0012588693
-
Contribution to the analysis of steam explosion using simplified models
-
CD-ROM, Texas A&M University, USA
-
Sardain, P., Robbe, M.F., Jevais, J.R., 2001. Contribution to the analysis of steam explosion using simplified models, ANS/HPS Student Conference '2001: a nuclear odyssey'. CD-ROM, Texas A&M University, USA.
-
(2001)
ANS/HPS Student Conference '2001: A Nuclear Odyssey'
-
-
Sardain, P.1
Robbe, M.F.2
Jevais, J.R.3
-
35
-
-
0003216294
-
The WINCON programme - Validation of the fast reactor primary containment codes
-
Walton D.G. (Ed.), Nuclear Containment Structures, Cambridge University Press
-
Sidoli, J.E.A., Kendall, K.C., 1988. The WINCON programme - validation of the fast reactor primary containment codes. In: Walton D.G. (Ed.), Proceedings of the INE International Conference on Nuclear Containment. Nuclear Containment Structures, Cambridge University Press.
-
(1988)
Proceedings of the INE International Conference on Nuclear Containment
-
-
Sidoli, J.E.A.1
Kendall, K.C.2
-
36
-
-
0001585542
-
A code comparison exercise based on the LMFBR containment experiment MARA-04
-
Section E4/7. Brussels, Belgium
-
Smith, B.L., Fiche, C., Louvet, J., Zucchini, A., 1985. A code comparison exercise based on the LMFBR containment experiment MARA-04. Proceedings of the Eighth International Conference on Structural Mechanics in Reactor Technology. Section E4/7. Brussels, Belgium, pp. 151-157.
-
(1985)
Proceedings of the Eighth International Conference on Structural Mechanics in Reactor Technology
, pp. 151-157
-
-
Smith, B.L.1
Fiche, C.2
Louvet, J.3
Zucchini, A.4
-
37
-
-
0000372898
-
Hydrogen combustion loads-plexus calculations
-
Struder E., Galon P. Hydrogen combustion loads-plexus calculations. Nuclear Engineering and Design. 174:1997;119-134.
-
(1997)
Nuclear Engineering and Design
, vol.174
, pp. 119-134
-
-
Struder, E.1
Galon, P.2
-
38
-
-
0002615840
-
On the origin of the discrepancies between theory and experiment in the COVA series
-
Lausanne, Switzerland
-
Wenger, H.U., Smith, B.L., 1987. On the origin of the discrepancies between theory and experiment in the COVA series. Proceedings of the Nineth International Conference on Structural Mechanics in Reactor Technology. Vol. E, Lausanne, Switzerland, pp. 339-344.
-
(1987)
Proceedings of the Nineth International Conference on Structural Mechanics in Reactor Technology
, vol.E
, pp. 339-344
-
-
Wenger, H.U.1
Smith, B.L.2
|