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STATE OF THE ART IN USING BEST ESTIMATE CALCULATION TOOLS IN NUCLEAR TECHNOLOGY  

D'AURIA FRANCESCO (Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione. Universita di Pisa)
ANIS BOUSBIA-SALAH (Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione. Universita di Pisa)
PETRUZZI ALESSANDRO (Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione. Universita di Pisa)
NEVO ALESSANDRO DEL (Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione. Universita di Pisa)
Publication Information
Nuclear Engineering and Technology / v.38, no.1, 2006 , pp. 11-32 More about this Journal
Abstract
System thermal-hydraulic codes have been used in the past decades in the areas of design, operation, licensing and safety of Nuclear Power Plants (NPPs). The development and validation of these codes have reached a high degree of maturity, through the consideration of huge experiments and advanced numerical models. Nowadays, the analyses are based upon realistic approaches rather than the conservative evaluation models. However the applications of these computational tools require preliminary qualification issues. Although huge amounts of financial and human resources have been invested for the development and improvement of codes, the calculation results are still affected by errors. In the sophisticated nuclear technology, design and safety of NPP, these errors must be quantified. An overview of the state of the art of the current thermal-hydraulic system code is developed and the need of uncertainty analysis in code calculations is emphasized. Several sources of uncertainty have been classified and commented, and typical applications of such methods are shown.
Keywords
NPP Accident Analysis; Best Estimate in System Thermal-hydraulics; Uncertainty; Quality of Predictions; User Effect; Scaling; Coupled Code;
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1 M. Leonardi, F. D'Auria, R. Pochard, 'Quantitative code accuracy evaluation of ISP-27 based on BETHSY Experiment', 2nd CAMP Meeting, Bruxelles (B), May 10-13, 1993
2 A. Petruzzi, F. D'Auria, 'Establishment of an Applicable Version of The CIAU Methodology', ICONE 13, Bejin, China, May 16-20, 2005
3 A. Petruzzi, F. D'Auria, 'Development, Qualification and Use of the CIAU Method for Internal Assessment of Uncertainty in System Codes', NURETH-11, Avignon, Oct., 2-6, 2005
4 C. Pretel, F. Reventos, L. Batet, 'Qualifying, validating and documenting a thermal-hydraulic code input deck', Advanced Thermal-hydraulic and Neutronic Codes: Current and Future Applications Summary and Conclusions OECD/CSNI Workshop Barcelona, Spain 10-13 April, 2000 - NEA/CSNI/R (2001)
5 Solis, J., Ivanov, K., Sarikaya, B., Olson, A., and Hunt, K. W., Boiling Water Reactor Turbine Trip (TT) Benchmark, Volume 1: Final specifications. NEA/NSC/DOC (2001)
6 F. D'Auria, G.M., Galassi, 'Code Validation and Uncertainties in System Thermal-hydraulics'. Prog. Nucl. En., 33, p.175, (1998)   DOI   ScienceOn
7 F. D'Auria (Lead Author), 'Neutronics/Thermal-hydraulics Coupling in LWR Technology: State-of-the-art Report (REAC-SOAR)'. CRISSUE-S-WP2, OCDE/NEA-5436. (2004)
8 F. D'Auria, E. Chojnacki, H. Glaeser, C. Lage, T. Wickett, 'Overview of Uncertainty Issues and Methodologies'. OECD/CSNI Seminar on Best Estimate Methods in Thermal Hydraulic Safety Analysis'. NEA/CSNI/R(99)10, (1999)
9 First Meeting of the BEMUSE program (Best-Estimate Methods - Uncertainty and Sensitivity Evaluation)- BEMUSE Phases 1 and 2, NEA/SEN/SIN/AMA27, (2003)
10 Ivanov K., Beam T. M., Baratta A. J., Irani A., Trikouros N., 'PWR Main Steam Line Break (MSLB) Benchmark - Volume I: Final Specifications', NEA/NSC/DOC(99)8 - Paris (F), April (1999)
11 R. Ashley, M. El-Shanawany, F. Eltawila, F. D'Auria, 'Good Practices for User Effect Reduction', OECD/CSNI Report NEA/CSNI/R(98)22, Paris (F), November (1998)
12 S. Belsito, F. D'Auria, G.M. Galassi, 'Application of a statistical model to the evaluation of Counterpart Test Database', Kerntechnik, 59, 3, (1994)
13 T. Wickett, F. D'Auria, H. Glaeser, E. Chojnacki, C. Lage, D. Sweet, A. Neil, G. M. Galassi, S. Belsito, M. Ingegneri, P. Gatta, T Skorek, E. Hoper, M. Kloos, M. Ounsy, and J. I. Sanchez, 'Report of the Uncertainty Method Study for Advanced Best Estimate Thermalhydraulic Code Applications', OECD/NEA/CSNI R (97) 35, Vols. I and II, June (1998)
14 F. D'Auria, J. L. Gago Moreno, G. M. Galassi, D. Grgic, and A. Spadoni, 'Three Mile Island Unit 1 Main Steam Line Break Three Dimensional Neutronics0Thermal-Hydraulics Analysis: Application of Different Coupled Codes', Nucl. Tec., 142, 180 (2003)   DOI
15 M. J. Lewis, R. Pochard, F. D'Auria, H. Karwat, K. Wolfert, G. Yadigaroglu, and H. L. O. Holmstrom 'Thermohydraulics of Emergency Core Cooling in Light Water Reactors-A State of the Art Report', OECD/CSNI 161, October (1989)
16 H. Helf, G. Bava, M. Champ, T. Raga, D. J. Hanson, H. L. O. Holmstrom, G. Jung, R. Mandl, J. Miettinen, S. A. Naff, B. Putter, and M. Tanaka, 'Catalogue of Generic Plant States Leading to Core Melt in PWRs' OECD/NEA/CSNI/R(96)18, November (1996)
17 A. Bousbia Salah, J. Vedovi, F. D'Auria, K. Ivanov, and G.M. Galassi, 'Analysis of the Peach Bottom Turbine Trip 2 Experiment by Coupled RELAP5-PARCS 3D Codes'. Nucl. Sci. Eng., 148, p.337, (2004)   DOI
18 S. Langenbuch, B. Krzykacz-Hausmann, K.D. Schmidt, G. Hegyi, A. Kereszturi, S. Kliem, J. Hadek, S. Danilin, S. Nikonov, A. Kuchin, V. Khalimanchuk, A. Hamalainen, 'Comprehensive uncertainty and sensitivity analysis for coupled code calculations of VVER plant transients', Nucl. Eng. Des., 235, p.52l, (2005)   DOI   ScienceOn
19 J. Vedovi., A. Bousbia Salah, F. D'Auria, G.M. Galassi, 'Analysis of The OECD/DOE/CEA VVER1000 CT-1 Benchmark Using RELAP5/PARCS Coupled Codes'. NURETH-11, France, Oct., 2-6, 2005
20 W. Ambrosini, D. Bestion, F. D'Auria, F. De Pasquale, J.C. Micaelli, M. Tempini, 'Application of the CATHARE Advanced Code to Numerical Benchnark Exercises'. EUROTHERM Seminar N. 7: Thermal Non-Equilibrium in Two-Phase Flow, Rome (I), March, 23-24, 1989
21 N. Aksan, F. D'Auria, H. Glaeser, R. Pochard, C. Richards, and A. Sjoberg, 'A Separate Effects Test Matrix for Thermal-Hydraulic Code Validation: Phenomena Characterization and Selection of Facilities and Tests', OECD/GD (94) 82, Vols. I and II, (1993)
22 A. Petruzzi, F. D'Auria, W. Giannotti, K. Ivanov, 'Methodology of internal assessment of uncertainty and extension to neutron kinetics/thermal-hydraulics coupled codes', Nucl. Sci. Eng., 149, p.1, (2005)   DOI
23 K. Trambauer, 'Computer and Compiler Effects on Code results Report' OECD/CSNI Report OCDE/GD(97) 6, Paris (1997)
24 A. Petruzzi, Extension of the CIAU Methodology for Uncertainty Evaluation in the Results of 3D Neutronics/Thermal-hydraulics Coupled Codes, Master Degree Thesis in Nuclear Engineering, University of Pisa, (2003)
25 S.N. Aksan, D. Bessette, I. Brittain, F. D'Auria, P. Gruber, H.L.O. Holmstrom, R. Landry, S. Naff, R. Pochard, G. Preusche, M. Reocreux, O. Sandervag, H. Stadtke, K. Wolfert, N. Zuber, 'Code Validation Matrix of Thermo-Hydraulic Codes for LWR LOCA and Transients'. CSNI Report N. 132, Paris (F), March, (1987)
26 F. D'Auria, P. Maugeri, 'Analysis by RELAP5/2 of a Loss of Feedwater Transient in the Leibstadt BWR-6 Plant'. International Conference on Thermal Reactor Safety, Avignon (F), 3-7 Oct., 1988
27 S. N. Aksan, F. D'Auria, H. Staedtke, 'User Effects on the Thermal-hydraulic Transient System Codes Calculations'. Nucl. Eng. Des., 145, 1&2, (1993)   DOI   ScienceOn
28 G. Yadigaroglu, A.J. Wickett, 'Report of a CSNI Workshop Uncertainty Analysis Methods'-NEA/CSNI/R(94)20, Paris (F) (1994)
29 F. D'Auria, N. Debrecin, G.M. Galassi, 'Outline of the Uncertainty Methodology based on Accuracy Extrapolation', Nucl. Tec., 109,1, p.21. (1995)
30 F. D'Auria, W. Giannotti, 'Development of Code with capability of Internal Assessment of Uncertainty'. Nucl. Tec, 131, (1), p.159, (2000)
31 M. Ishii, S.Kim and J. Ulhe, 'Interfacial Area Transport: Data and Models', OECD/CSNI Workshop on Advanced Thermal-Hydraulic and Neutronic Codes, Barcelona (Spain), April 10-14, 2000
32 N. Zuber, G.E. Wilson, B.E. Boyack, I. Catton, R.B Duffey, P. Griffith, K.R. Katsma, G.S. Lellouche, S. Levy, U.S. Rohatgi, W. Wulff, 'Evaluation of scale up capabilities of best estimate codes', Nucl. Eng. Des., 119, p.9, (1990)   DOI   ScienceOn
33 W. Ambrosini, R. Bovalini, F. D'Auria, 'Evaluation of Accuracy of Thermal-hydraulic Codes Calculations', Energia Nucleare, 7, 2, (1990)
34 A. Petruzzi, F. D'Auria, W. Giannotti, 'Approach and Method to Evaluate the Uncertainty in System Thermal-Hydraulics Calculations. Key Applications', IAEA TCM Use of a Best Estimate Approach in Licensing with Evaluation of Uncertainties Pisa - Sept., 12-16, 2005
35 Wilson G. E., Boyack B.,E., Catton I., Duffey R.B., Griffith P., Katsma K.R., Lellouche G.S., Levy S., Rohatgi U.S., Shaw A., Wilson G.E., ..Wulff W., Zuber N., 'Characterization of important contributions to uncertainty', Nucl. Eng. Des., Vol. 119, p.17, (1990)   DOI   ScienceOn
36 Boyack B.E., Cat ton I., Duffey R.B-, Griffith P., Katsrna K.R., Lellouche G.S., Levy S., Rohatgi U.S., Wilson G.E., Wulff W., Zuber N.: 'An: overview of the code scaling, applicability and uncertainty evaluation methodology', Nucl. Eng. Des., 119, p.1, (1990)   DOI   ScienceOn
37 R.F. Kunz, G.F Kasmala, J.H. Mahaffy, C.J Murray, 'On the automated assessment of nuclear reactor system code accuracy', Nucl. Eng. Des., 211, 2-3, (2002)   DOI   ScienceOn
38 F. Reventos, C. Llopis, 'Benefits of using integral plant models in utilities availability and safety issues', Advanced Thermal-hydraulic and Neutronic Codes: Current and Future Applications Summary and Conclusions OECD/CSNI Workshop Barcelona, Spain 10-13 April, 2000 - NEA/CSNI/R (2001)
39 F. D'Auria, 'Nodalisation Development and Qualification'. IAEA TCM on Inter-comparison and Validation of Computer Codes for Thermal-hydraulic Safety Analyses of Heavy Water Reactors, Vienna, 2000
40 A. Bousbia Salah, S. Kliem, U. Rohde, F. D'Auria, A. Petruzzi,' Uncertainty and sensitivity analyses of the Kozloduy pump trip test using coupled thermal-hydraulic 3D kinetics code', In press Nucl. Eng. and Des., (2006)   DOI   ScienceOn
41 I. Stanev, F. D'Auria, 'Analysis of LOCA D=200 mm for Kozloduy - Units 3&4 with RELAP5/3.2 and CATHARE codes. Evaluation of the results uncertainty', IAEA TCM on Safety Margins of Operating Reactors and Implications for Decisions Makers including consideration of Uncertainties of Analysis, Vienna (A), Oct., 15-19, 200l
42 D'Auria F.(Editor), Ambrosini W., Anegawa T., Blomstrand J., In De Betou J., Langenbuch S., Lefvert T., Valtonen K., 'State of the Art Report on Boiling Water Reactor Stability (SOAR on BWR)', OECD-CSNI Report OECD/GD (97) 13, Paris (F), Jan. (1997)
43 G. Yadigaroglu, D. Lakehal, 'New Challenges In Computational Thermal Hydraulics', Nucl. Tec., 152, p.239, (2005)   DOI
44 A. Bousbia Salah, 'Overview of coupled system thermal-hydraulic-3D neutron kinetics code applications'. Ph.D Thesis, Ref: 17033. Universita di Pisa, (2004)
45 F. D'Auria, G. M. Galassi, 'Best Estimate Analysis and Uncertainty evaluation of the Angra-2 LBLOCA DBA', University of Pisa Report, DIMNP-NT 433(01), Pisa (I)-rev.1, July, 200l