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Code of Federal Regulations
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Code validation matrix of thermalhydraulic codes for LWR LOCA and transients
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Evaluation of licensing margins of operating reactors using 'best estimate' methods including uncertainty analysis
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5th Seminar on Scaling, Uncertainty and 3D Coupled Code Calculations in Nuclear Technology (3D S.UN.COP)
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Glaeser, H.1
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33845742934
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NEA/CSNI/ R (96) 19, Organisation for Economic Co-operation and Development, Nuclear Energy Agency, Committee on the Safety of Nuclear Installations
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"CSNI Status Summary on Utilization of Best-Estimate Methodology in Safety Analysis and Licensing," NEA/CSNI/ R (96) 19, Organisation for Economic Co-operation and Development, Nuclear Energy Agency, Committee on the Safety of Nuclear Installations (1996).
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F. D'AURIA, "The Origin of the Uncertainties," presented at 7th Seminar on Scaling, Uncertainty and 3D Coupled Code Calculations in Nuclear Technology (3D S.UN.COP), College Station, Texas, January 22-February 9, 2007.
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7th Seminar on Scaling, Uncertainty and 3D Coupled Code Calculations in Nuclear Technology (3D S.UN.COP)
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D'Auria, F.1
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70350572711
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Planning of counterpart tests in LWR experimental simulators
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Houston, Texas, July 24-27, 1988, American Nuclear Society
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Outline of the uncertainty methodology based on accuracy extrapolation
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An overview of westinghouse realistic large break LOCA evaluation model
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"Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition," NUREG0800, Chap. 15, "Transient and Accident Analysis," Sec. 15.0.2, "Review of Transient and Accident Analysis Method," U.S. Nuclear Regulatory Commission (Dec. 2005).
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Development considerations of AREVA NP Inc.'s realistic LBLOCA analysis methodology
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Martin, R.P.1
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GRS method for uncertainty and sensitivity evaluation of code results and applications
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84872739438
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Best estimate and uncertainty analysis for CANDU reactors
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presented at Hamilton, Ontario, Canada, October 8-26
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N. POPOV, "Best Estimate and Uncertainty Analysis for CANDU Reactors," presented at 8th Seminar on Scaling, Uncertainty and 3D Coupled Code Calculations in Nuclear Technology (3D S.UN.COP), Hamilton, Ontario, Canada, October 8-26, 2007.
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8th Seminar on Scaling, Uncertainty and 3D Coupled Code Calculations in Nuclear Technology (3D S.UN.COP)
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Popov, N.1
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29
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Application of code scaling applicability and uncertainty methodology to the large break loss of coolant
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M. Y. YOUNG, S. M. BAJOREK, M. E. NISSLEY, and L. E. HOCHREITER, "Application of Code Scaling Applicability and Uncertainty Methodology to the Large Break Loss of Coolant," Nucl. Eng. Des., 186, 39 (1998).
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Nucl. Eng. Des.
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Young, M.Y.1
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30
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0032206536
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Application of the WCOBRA/TRAC best estimate methodology to the AP600 large-break LOCA analysis
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J. ZHANG, S. M. BAJOREK, R. M. KEMPER, M. E. NISSLEY, N. PETKOV, and L. E. HOCHREITER, "Application of the WCOBRA/TRAC Best Estimate Methodology to the AP600 Large-Break LOCA Analysis," Nucl. Eng. Des., 186, 279 (1998).
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Zhang, J.1
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31
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27744520940
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Application of best-estimate methods to LOCA in a PWR
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presented at Ankara, Turkey, Organisation for Economic Co-operation and Development, Committee on the Safety of Nuclear Installations
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F. DEPISCH, G. SEEBERGER, and S. BLANK, "Application of Best-Estimate Methods to LOCA in a PWR," presented at Seminar on Best Estimate Methods in ThermalHydraulic Safety Analysis, Ankara, Turkey, Organisation for Economic Co-operation and Development, Committee on the Safety of Nuclear Installations (1998).
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(1998)
Seminar on Best Estimate Methods in Thermal Hydraulic Safety Analysis
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Depisch, F.1
Seeberger, G.2
Blank, S.3
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32
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44349129042
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Development and application of ontario power generation's best estimate nuclear safety analysis methodology
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Washington, D.C., November 2000, American Nuclear Society CD-ROM
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J. C. LUXAT, R. G. HUGET, F. TRAN, and D. K. LAU, "Development and Application of Ontario Power Generation's Best Estimate Nuclear Safety Analysis Methodology," Proc. Int. Mtg. Best Estimate Methods in Nuclear Installations Safety Analysis (BE-2000), Washington, D.C., November 2000, American Nuclear Society (2000) (CD-ROM).
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Proc. Int. Mtg. Best Estimate Methods in Nuclear Installations Safety Analysis (BE-2000)
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Luxat, J.C.1
Huget, R.G.2
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Lau, D.K.4
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Best estimate methods for safety margin assessment
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Washington, D.C., November 2000, American Nuclear Society CD-ROM
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H. E. SILLS, A. ABDUL-RAZZAK, R. B. DUFFEY, and N. POPOV, "Best Estimate Methods for Safety Margin Assessment," Proc. Int. Mtg. Best Estimate Methods in Nuclear Installations Safety Analysis (BE-2000), Washington, D.C., November 2000, American Nuclear Society (2000) (CD-ROM).
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Proc. Int. Mtg. Best Estimate Methods in Nuclear Installations Safety Analysis (BE-2000)
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Sills, H.E.1
Abdul-Razzak, A.2
Duffey, R.B.3
Popov, N.4
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35
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LBLOCA analysis using the deterministic realistic methodology-application to the 3-loop plant
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presented at Tokyo, Japan
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M. LUDMANN and J. Y. SAUVAGE, "LBLOCAAnalysis Using the Deterministic Realistic Methodology-Application to the 3-Loop Plant," presented at 7th Int. Conf. Nuclear Engineering, Tokyo, Japan, 1999.
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7th Int. Conf. Nuclear Engineering
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Ludmann, M.1
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0343345567
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NEA/CSNI/ R (98) 22, Organisation for Economic Co-operation and Development, Nuclear Energy Agency, Committee on the Safety of Nuclear Installations
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"Good Practices for User Effect Reduction," NEA/CSNI/ R (98) 22, Organisation for Economic Co-operation and Development, Nuclear Energy Agency, Committee on the Safety of Nuclear Installations (1998).
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77958137281
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Proc. OECD/CSNI Workshop Transient Thermal-Hydraulic and Neutronic Codes Requirements, Annapolis, Maryland, November 5-8,1996, and NUREG/CP-0159, U.S. Nuclear Regulatory Commission, and NEA/CSNI/R(97)4, Organisation for Economic Co-operation and Development, Nuclear Energy Agency, Committee on the Safety of Nuclear Installations (1997).
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Proc. OECD/CSNI Workshop Transient Thermal-hydraulic and Neutronic Codes Requirements
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NEA/CSNI/R(99)22, Organisation for Economie Co-operation and Development, Nuclear Energy Agency, Committee on the Safety of Nuclear Installations
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"Best-Estimate Methods in Thermal Hydraulic Safety Analysis, Summary and Conclusions of an OECD-CSNI Seminar," NEA/CSNI/R(99)22, Organisation for Economie Co-operation and Development, Nuclear Energy Agency, Committee on the Safety of Nuclear Installations (1999).
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Best-Estimate Methods in Thermal Hydraulic Safety Analysis, Summary and Conclusions of An OECD-CSNI Seminar
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39
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Methodology of internal assessment of uncertainty and extension to neutron kinetics/thermal-hydraulics coupled codes
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A. PETRUZZI, F. D'AURIA, W GIANNOTTI, and K. IVANOV, "Methodology of Internal Assessment of Uncertainty and Extension to Neutron Kinetics/Thermal-Hydraulics Coupled Codes," Nucl. Sci. Eng., 149, 211 (2005).
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Nucl. Sci. Eng.
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Petruzzi, A.1
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77958142898
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Regulatory scenario for the acceptance of uncertainty analysis methodologies for the LBLOCA and the Brazilian approach
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M. R. GALETTI, "Regulatory Scenario for the Acceptance of Uncertainty Analysis Methodologies for the LBLOCA and the Brazilian Approach," Sci. Technol. Nucl. Installations, Special Issue 2008 (2008).
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Sci. Technol. Nucl. Installations
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Galetti, M.R.1
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44349135078
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Internal DIMNP NT 440(01), Rev.0, University of Pisa
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F. D'AURIA, G. M. GALASSI, and W. GIANNOTTI, "Confirmatory Safety Analyses Carried Out by Relap5 and Cathare Codes Related to the Kozloduy VVER 440/230 Unit No 3," Internal DIMNP NT 440(01), Rev.0, University of Pisa (2001).
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Confirmatory Safety Analyses Carried out by Relap5 and Cathare Codes Related to the Kozloduy VVER 440/230 Unit No 3
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D'Auria, F.1
Galassi, G.M.2
Giannotti, W.3
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43
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70349316267
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RELAP5 simulation of surge line break accident using combined and best estimate plus uncertainty approaches
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M. KRIŠTOF, T. KLIMENT, A. PETRUZZI, and J. LIPKA, "RELAP5 Simulation of Surge Line Break Accident Using Combined and Best Estimate Plus Uncertainty Approaches," Nucl. Eng. Des., 239, 11, 2500 (2009).
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Nucl. Eng. Des.
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Krištof, M.1
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85036763977
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Requirements on deterministic safety analysis of nuclear power plants
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BNS I.11.1/2008, Nuclear Regulatory Authority of the Slovak Republic
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J. HUSÁRČEK and M. KRIŠTOF, "Requirements on Deterministic Safety Analysis of Nuclear Power Plants," ÚJD SR Regulatory Guide, BNS I.11.1/2008, Nuclear Regulatory Authority of the Slovak Republic (2008).
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ÚJD SR Regulatory Guide
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Husárček, J.1
Krištof, M.2
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46
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85036742718
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BEPU approach for the licensing process of Atucha-2 NPP
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presented at Budapest, Hungary, September 15-19
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C. CAMARGO, M. R. GALETTI, F. D'AURIA, N. MUELLNER, A. PETRUZZI, and O. MAZZANTINI, "BEPU Approach for the Licensing Process of Atucha-2 NPP," presented at International Atomic Energy Agency Technical Mtg. The Use of Safety Margins and Advance Safety Assessment Methods in Plant Modifications, Budapest, Hungary, September 15-19, 2008.
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International Atomic Energy Agency Technical Mtg. The Use of Safety Margins and Advance Safety Assessment Methods in Plant Modifications
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Camargo, C.1
Galetti, M.R.2
D'Auria, F.3
Muellner, N.4
Petruzzi, A.5
Mazzantini, O.6
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