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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
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A. Petruzzi, F. D'Auria, 'Establishment of an Applicable Version of The CIAU Methodology', ICONE 13, Bejin, China, May 16-20, 2005
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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
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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)
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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)
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F. D'Auria, G.M., Galassi, 'Code Validation and Uncertainties in System Thermal-hydraulics'. Prog. Nucl. En., 33, p.175, (1998)
DOI
ScienceOn
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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)
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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)
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First Meeting of the BEMUSE program (Best-Estimate Methods - Uncertainty and Sensitivity Evaluation)- BEMUSE Phases 1 and 2, NEA/SEN/SIN/AMA27, (2003)
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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)
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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)
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S. Belsito, F. D'Auria, G.M. Galassi, 'Application of a statistical model to the evaluation of Counterpart Test Database', Kerntechnik, 59, 3, (1994)
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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)
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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
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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)
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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)
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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
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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
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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
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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
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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)
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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
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K. Trambauer, 'Computer and Compiler Effects on Code results Report' OECD/CSNI Report OCDE/GD(97) 6, Paris (1997)
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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)
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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)
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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
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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
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G. Yadigaroglu, A.J. Wickett, 'Report of a CSNI Workshop Uncertainty Analysis Methods'-NEA/CSNI/R(94)20, Paris (F) (1994)
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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)
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30 |
F. D'Auria, W. Giannotti, 'Development of Code with capability of Internal Assessment of Uncertainty'. Nucl. Tec, 131, (1), p.159, (2000)
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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
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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)
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W. Ambrosini, R. Bovalini, F. D'Auria, 'Evaluation of Accuracy of Thermal-hydraulic Codes Calculations', Energia Nucleare, 7, 2, (1990)
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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
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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)
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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)
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ScienceOn
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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
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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)
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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
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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
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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
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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)
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G. Yadigaroglu, D. Lakehal, 'New Challenges In Computational Thermal Hydraulics', Nucl. Tec., 152, p.239, (2005)
DOI
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A. Bousbia Salah, 'Overview of coupled system thermal-hydraulic-3D neutron kinetics code applications'. Ph.D Thesis, Ref: 17033. Universita di Pisa, (2004)
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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
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