More than 30 years of reactor thermal hydraulics

Kerntechnik

Volumn 63, Issue 1-2, 1998, Pages 8-17

  D'Auria, F ^a   Wahba, A B ^b  

^a UNIVERSITY OF PISA   (Italy)

^b Gesell F Anlagen R   (Germany)

Author keywords

[No Author keywords available]

Indexed keywords

DIES; LIGHT WATER REACTORS; HYDRAULICS; WATER COOLED REACTORS;

'CURRENT; ACCIDENT CONDITIONS; COMPUTER CODES; DEVELOPMENTAL STAGE; EXPERIMENTAL RESEARCH; HYDRAULIC RESEARCH; REACTOR THERMAL HYDRAULICS; RESEARCH PROGRAMS; SYSTEM CODES; UNCERTAINTY;

CODES (SYMBOLS); LIGHT WATER REACTORS;

REACTOR THERMAL HYDRAULICS;

EID: 0031997275     PISSN: 09323902     EISSN: None     Source Type: Journal    
DOI: None     Document Type: Article

References (33)

1. Wahba, A. B. and Hicken, E. F.: Ten years of experimenting in the Loss of Fluid Test (LOFT) facility, Atomkernenergie-Kerntechnik 49 (1986) 68
2. D'Auria, F. and Karwat, H.: OECD/CSNI-SOAR on TECC: Experimentalprograms OECD/CSNI Document, Sindoc (89) 101, Paris (F), Aug. 1989
3. D'Auria, F.; Debrecin, N.; Galassi, G. M.; Galeazzi, S.: Application of RELAP5/Mod3 to the evaluation of Loss of Feedwater in test facilities and in nuclear plants, J. Nucl. Eng. and Design 141 (1993) 409
4. Ishii, M.; Kataoka, I.: Scaling criteria for LWR's under single phase and two phase Natural Circulation, ANL Report, ANL-83-32, NUREG/CR 3267, March 1983
5. Damerell, P. S.; Simons, J. W. (Editors): Reactor Safety Issues resolved by the 2D/3D Program, US NRC Report NUREG/IA-0127, Washington DC, July 1993
6. Mayinger, F.; Weiss, P.; Wolfert, K.: Two-phase flow phenomena in full scale reactor geometry, J. Nucl. Eng. and Design 145 (1993) 47
7. Glaeser, H.; Karwat, H.: The contribution of UPTF experiments to resolve some scale-up uncertainties in countercurrent two-phase flow, J. Nucl. Eng. and Design 145 (1993) 63
8. D'Auria, F.; Galassi, G. M.; Oriolo, F.; Fruttuoso, G.: Evaluation of RELAP5/Mod3.1 application to Spes-2 experiments, Int. Meet. on Advanced Reactor Safety, Orlando (Fl), 1-5 June 1997
9. Nakamura, H.; Kukita, Y.; Ghan, L. S.; Schultz, R. R.: Rosa-AP-600 experiment simulating a steam generator Tube rupture transient, Int. Meet. on Advanced Reactor Safety, Orlando (Fl), 1-5 June 1997
10. Karwat, H. and Wolfert, K.: BRUCH-D A digital Program for Pressurized Water Reactor Blowdown Investigation, J. Nucl. Eng. and Design 11 (1970) 241
11. Wolfert, K.: The simulation of Blowdown Processes with consideration of thermodynamic nonequilibrium phenomena, OECD/ NEA Specialists Meeting on Transient Two Phase Flow, Toronto, Canada, August 1976
12. Steinhoff, F.: Berücksichtigung der Phasenseparation und Gemischspiegeldynamik bei der Simulation von Druckentladungsvorgängen, Kerntechnik 54 (1989) 162
13. Wahba, A. B. and Wolfert, K.: Influence of scaling of the Battelle BWR Test Facility on the analysis of experimental results, Proceedings of the joint NRC/ANS Meeting on basic thermal hydraulic Mechanisms in LWR analysis NUREG/CP-0043 April 83
14. Teschendorff, V.; Wahba, A. B.: Simultane Berechnung der Wasserstände und Hüllrohrtemperaturen während der Wiederauffüllung und Flutphase der Kernnotkühlung eines Druckwasserreaktors, Fachtagung der Kerntechnischen Gesellschaft, Mannheim 1977
15. Hora, A.; Michetschläger, C.; Sonnenburg, H. G.; Teschendorff, V.: Analysis of Refload Phenomena by the Two-Fluid Code FLUT, Advances in Two-Phase Flow and Heat Transfer, M. Nijhoff Publ., den Haag 1983
16. Frisch, W. and Schmidt, K. D.: A PWR Plant Model for the Analysis of Large Amplitude Transients, 3nd Power Plant Dynamics, Control and Testing Symposium, Knoxville, Tennessee, USA, 1977
17. Schaefer, A.; Miro, J. E.; Hoeppner, G.; Frisch, W.; Meissner, R.; Gaal, U.: ALMOD Advanced PWR Transient Analysis Code, Proc. ANS Topical Meeting on Anticipated and abnormal Plant Transients in light water Reactors, Jakson, Wyoming, USA, 1983
18. Wolfert, K.; Lerchl, G.; Miro, J. and Sonnenburg, H.: The GRS Thermal hydraulic System Code ATHLET for PWR and BWR Analyses, 3nd International topical Meeting on Nuclear Power Plant Thermal Hydraulics and Operation, Seoul, Korea, Nov. 1988
19. D'Auria, F.; Galassi, G. M.: Code validation and uncertainties in system thermal hydraulics, J. Progress in Nuclear Energy, August 1997
20. Glaeser, H.; Liesch, K.: The benefit of Validation matrices for thermal hydraulic computer codes, Kerntechnik 63 (1998)
21. D'Auria, F.; Galassi, G. M.: Assessment of RELAP5/Mod2 on the basis of experiments performed in LOBI facility, J. Nuclear Technology 90 (1990) no 3
22. D'Auria, F.; Galassi, G. M.; Madeira, A.: Effect of minor boundary conditions on dryout during small LOCA in PWRs, X Brazilian Meeting on Reactor Physics and Thermal Hydraulics - Aguas de Lindoia (SP), 7-11 Aug. 1995
23. Aksan, S. N.; D'Auria, F.; Staedtke, H.: User effect on the thermalhydraulic Transient System Codes Calculations, J. Nucl. Eng. and Design 145 (1995) 159
24. D'Auria, F.; Eramo, M.; Frogheri, M.; Galassi, G. M.: Accuracy quantification in SPE-1 to SPE-4 organized by IAEA, ASME-JSME Int. Conf. on Nuclear Engineering (ICONE-4) - New Orleans (LO), 10-14 March 1996
25. Bonuccelli, M.; D'Auria, F.; Debrecin, N.; Galassi, G. M.: A methodology for the qualification of thermalhydraulic codes nodalizations, 6th Int. Top. Meet. on Nuclear Reactor Thermalhydraulics (NURETH-6), Grenoble (F), 5-8 Oct. 1993
26. Zuber, N.; Wilson, G.; Boyack, B.; Catton, I.; Duffey, R. B.; Griffith, P.; Katsma, K.; Lellouche, G.; Levy, S.; Rohatgi, U. S.; Wulff, W.: Evaluation of scale-up capabilities of Best Estimate Codes, J. Nucl. Eng. and Design 119 (1990)
27. Hofer, E.: The GRS Programme Package for Uncertainty and Sensitivity Analysis, Seminar on Methods and Codes for assessing the Off-Site Consequences of Nuclear Accidents, CEC-EUR 13013, Brussels, May 1990
28. D'Auria, F., Debrecin, N., Galassi, G. M.: Outline of the Uncertainty Methodology based on Accuracy Extrapolation (UMAE), J. Nuclear Technology (1995)
29. Wickett, A. J., Neil, A. P.: Advanced LOCA Code Uncertainty Assessment: A Pilot Study, AEA Report AEEW-R2508, Winfrith (UK), Nov. 1990
30. D'Auria, F.; Leonardi, M.; Glaeser, H.; Pochard, R.: Current Status of Methodologies evaluating the Uncertainty in the prediction of thermal hydraulic phenomena in Nuclear reactors, Int. Conf. on Two-Phase Flow Modelling and Experimentation, Roma (I), 9-11 Oct. 1995
31. Wickett, A. J. (Editor); D'Auria, F.; Glaeser, H.; Chojnacki, E.; Lage, C. (Lead Authors): Report of the Uncertainty Method Study (UMS) for advanced Best Estimate Thermalhydraulic codes Applications, OECD/CSNI Report, June 1997
32. OECD/CSNI: Proceedings of the Workshop on Transient Thermalhydraulic and Neutronic Codes Requirements Annapolis (MD), 5-8 Nov. 1996
33. D'Auria, F.; Eramo, A.; Giannotti, W.: Advancements in planning an IAU Code, 4th Regional Meeting Nuclear Energy in Central Europe, Bled (Slo), 7-10 Sept. 1997