Qualification of Coupled 3-D Neutron-Kinetic/Thermal-Hydraulic Code Systems by the Calculation of Main-Steam-Line-Break Benchmarks in an NPP with VVER-440 Reactor

REFERENCES

• S. MITTAG et al., “Validation of Coupled Neutron Kinetic/Thermal-Hydraulic Codes, Part 1: Analysis of a VVER-1000 Transient (Balakovo-4),” Ann. Nucl. Energy, 28/9, 857 (2001).
   Google Scholar
• A. HÄMÄLÄINEN et al., “Validation of Coupled Neutron Kinetic/Thermal-Hydraulic Codes, Part 2: Analysis of a VVER-440 Transient (Loviisa-1),” Ann. Nucl. Energy, 29/5, 255 (2002).
   Google Scholar
• T. VANTTOLA et al., “Validation of Coupled Codes Using VVER Plant Measurements,” Nucl. Eng. Des., 235, 507 (2005).
   Google Scholar
• K. N. IVANOV, N. K. TODOROVA, and E. SARTORI, “Using the OECD/NRC Pressurized Water Reactor Main Steam Line Break Benchmark to Study Current Numerical and Computational Issues of Coupled Calculations,” Nucl. Technol., 142, 95 (2003).
   Web of Science ®Google Scholar
• K. IVANOV, A. OLSON, and E. SARTORI, “OECD/NRC BWR Turbine Trip Transient Benchmark as a Basis for Comprehensive Qualification and Studying Best-Estimate Coupled Codes,” Nucl. Sci. Eng., 148, 195 (2004).
   Web of Science ®Google Scholar
• M. TELBISZ and A. KERESZTÚRI, “Results of a Three-Dimensional Hexagonal Kinetic Benchmark Problem,” Proc. 3rd Symp. Atomic Energy Research (AER) for Investigating Neutron Physics and Thermohydraulics Problems of Reactor Safety, Piestany, Slovakia, September 27–October 1, 1993, p. 217, KFKI Atomic Energy Research Institute (1993).
   Google Scholar
• U. GRUNDMANN, “Results of the Second Kinetic AER Benchmark,” Proc. 4th Symp. Atomic Energy Research (AER) for Investigating Neutron Physics and Thermohydraulics Problems of Reactor Safety, Sozopol, Bulgaria, October 10–15, 1994, p. 397, KFKI Atomic Energy Research Institute (1994).
   Google Scholar
• R. KYRKI-RAJAMÄKI and E. KALOINEN, “Results of the Third Three-Dimensional Hexagonal Dynamic AER Benchmark Problem Including Thermal Hydraulics Calculations in the Core and a Hot Channel,” Proc. 5th Symp. Atomic Energy Research (AER) for Investigating Neutron Physics and Thermohydraulics Problems of Reactor Safety, Dobogokö, Hungary, October 15–19, 1995, p. 255, KFKI Atomic Energy Research Institute (1995).
   Google Scholar
• R. KYRKI-RAJAMÄKI, “Comparison of the First Results of the 4th Hexagonal Dynamic AER Benchmark, Boron Dilution in the Core,” Proc. 7th Symp. Atomic Energy Research (AER) on VVER Reactor Physics and Reactor Safety, Hörnitz, Germany, September 23–26, 1997, p. 321, KFKI Atomic Energy Research Institute (1997).
   Google Scholar
• R. KYRKI-RAJAMÄKI, U. GRUNDMANN, and A. KERESZTÚRI, “Results of Three-Dimensional Hexagonal Dynamic Benchmark Problems for VVER Type Reactors,” Proc. Int. Conf. Physics of Reactors (PHYSOR96), Mito, Japan, September, 1996, p. J-229 (1996).
   Google Scholar
• R. KYRKI-RAJAMÄKI, “Results of a 3D Reactor Dynamics Benchmark Problem on Boron Dilution in the Core,” Proc. Int. Conf. Physics of Nuclear Science and Technology, Long Island, New York, October 5–8, 1998, Vol. 2, p. 1537, American Nuclear Society (1998).
   Google Scholar
• S. DANILIN, M. LIZORKIN, and V. PEKHTEREV, “Solution of the 5th AER Benchmark with Code Package ATHLET/BIPR8KN,” Proc. 8th Symp. Atomic Energy Research (AER) on VVER Reactor Physics and Reactor Safety, Bystrice nad Pernstejnem, Czech Republic, September 21–25, 1998, p. 405, and KFKI Atomic Energy Research Institute (1998).
   Google Scholar
• S. DANILIN, M. LIZORKIN, and S. NIKONOV, “The New Solution of the AER Sixth Benchmark Problem with ATHLET/BIPR8KN Code Package,” Proc. 12th Symp. Atomic Energy Research (AER) on VVER Reactor Physics and Reactor Safety, Nessebar, Bulgaria, September 22–28, 2002, p. 333, KFKI Atomic Energy Research Institute (2002).
   Google Scholar
• A. HÄMÄLÄINEN, R. KYRKI-RAJAMÄKI, “The 5th AER Dynamic Benchmark Calculation with HEXTRAN/SMABRE,” Proc. 8th Symp. Atomic Energy Research (AER) on VVER Reactor Physics and Reactor Safety, Bystrice nad Pernstejnem, Czech Republic, September 21–25, 1998, p. 369, KFKI Atomic Energy Research Institute (1998).
   Google Scholar
• A. HÄMÄLÄINEN and R. KYRKI-RAJAMÄKI, “HEXTRAN-SMABRE Calculations of the 6th Dynamic AER Benchmark—Main Steam Line Break in a VVER440 NPP,” Proc. 13th Symp. Atomic Energy Research (AER) on VVER Reactor Physics and Reactor Safety, Dresden, Germany, September 22–26, 2003, p. 445, KFKI Atomic Energy Research Institute (2003).
   Google Scholar
• J. HÁDEK and R. MECA, “Results of the 5th 3-Dimensional Dynamic AER Benchmark Problem Calculations,” Proc. 8th Symp. Atomic Energy Research (AER) on VVER Reactor Physics and Reactor Safety, Bystrice nad Pernstejnem, Czech Republic, September 21–25, 1998, p. 389, KFKI Atomic Energy Research Institute (1998).
   Google Scholar
• J. HÁDEK and P. KRAL, “Final Results of the 6th Three-Dimensional AER Dynamic Benchmark Problem Calculation. Solution with DYN3D and RELAP5-3D Codes,” Proc. 13th Symp. Atomic Energy Research (AER) on VVER Reactor Physics and Reactor Safety, Dresden, Germany, September 22–26, 2003, p. 459, KFKI Atomic Energy Research Institute (2003).
   Google Scholar
• S. KLIEM, “Comparison of the Results of the 5th Dynamic AER Benchmark—A Benchmark for Coupled Thermohydraulic System/3D Hexagonal Neutron Kinetic Core Models,” Proc. 8th Symp. Atomic Energy Research (AER) on VVER Reactor Physics and Reactor Safety, Bystrice nad Pernstejnem, Czech Republic, September 21–25, 1998, p. 429, KFKI Atomic Energy Research Institute (1998).
   Google Scholar
• S. KLIEM, “Comparison of the Updated Solutions of the 6th Dynamic AER Benchmark—Main Steam Line Break in a NPP with VVER-440,” Proc. 13th Symp. Atomic Energy Research (AER) on VVER Reactor Physics and Reactor Safety, Dresden, Germany, September 22–26, 2003, p. 413, KFKI Atomic Energy Research Institute (2003).
   Google Scholar
• S. KLIEM, “Solution of the 5th Dynamic AER Benchmark Using the Coupled Code DYN3D/ATHLET,” Proc. 8th Symp. Atomic Energy Research (AER) on VVER Reactor Physics and Reactor Safety, Bystrice nad Pernstejnem, Czech Republic, September 21–25, 1998, p. 357, KFKI Atomic Energy Research Institute (1998).
   Google Scholar
• A. SEIDEL and S. KLIEM, “Solution of the 6th Dynamic AER Benchmark Using the Coupled Code DYN3D/ATHLET,” Proc. 11th Symp. Atomic Energy Research (AER) for Investigating Neutron Physics and Thermohydraulics Problems of Reactor Safety, Csopak, Hungary, September 24–28, 2001, p. 251, KFKI Atomic Energy Research Institute (2001).
   Google Scholar
• V. TESCHENDORFF, H. AUSTREGESILO, and G. LERCHL, “Methodology, Status and Plans for Development and Assessment of the Code ATHLET,” Proc. Workshop Transient Thermal-Hydraulic and Neutronic Codes Requirements, Annapolis, Maryland, November 5–8, 1996, p. 112, Organisation for Economic Co-operation and Development Committee on the Safety of Nuclear Installations (1996).
   Google Scholar
• H. AUSTREGESILO, C. BALS, A. HORA, G. LERCHL, and P. ROMSTEDT, “ATHLET, Mod 2.0 Cycle A, Models and Methods,” GRS-P-1/Vol. 4, Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH (2003).
   Google Scholar
• “RELAP5-3D© Code Manuals Volume I: Code Structure, System Models and Solution Methods; Volume II: User’s Guide and Input Requirements; Volume IV: Models and correlations; Volume V: User’s guidelines,” INEEL-EXT-98-00834, Idaho National Engineering and Environmental Laboratory (1999).
   Google Scholar
• J. MIETTINEN and A. HÄMÄLÄINEN, “Development and Validation of the Fast Running Thermohydraulic Model SMABRE for Simulator Purposes,” Proc. 8th Int. Conf. Nuclear Engineering (ICONE-8), Baltimore, Maryland, April 2–6, 2000 (2000).
   Google Scholar
• U. GRUNDMANN, U. ROHDE, and S. MITTAG, “DYN3D—Three Dimensional Core Model for Steady-State and Transient Analysis of Thermal Reactors,” Proc. Int. Topl. Mtg. Advances in Reactor Physics and Mathematics and Computation into the Next Millennium (PHYSOR 2000), Pitts-burgh, Pennsylvania, May 7–12, 2000, American Nuclear Society (2000) (CD-ROM).
   Google Scholar
• A. MANERA, U. ROHDE, H.-M. PRASSER, and T. H. J. J. VAN DER HAGEN, “Modeling of Flashing-Induced Instabilities in the Start-Up Phase of Natural-Circulation BWRs Using the Code FLOCAL,” Nucl. Eng. Des., 235, 1517 (2005).
   Web of Science ®Google Scholar
• R. KYRKI-RAJAMÄKI, “Three-Dimensional Reactor Dynamics Code for VVER Type Reactors,” VTT publications 246, Technical Research Centre of Finland (1995).
   Google Scholar
• A. KERESZTÚRI, GY. HEGYI, CS. MARÁCZY, I. PANKA, M. TELBISZ, I. TROSZTEL, AND CS. HEGEDŰS, “Development and Validation of the Three-Dimensional Dynamic Code—KIKO3D,” Ann. Nucl. Energy, 30, 93 (2003).
   Web of Science ®Google Scholar
• M. P. LIZORKIN, V. N. SEMENOV, V. S. IONOV, and V. I. LEBEDEV, “Time Dependent Spatial Neutron Kinetic Algorithm for BIPR8 and Its Verification,” Proc. 2nd Symp. Atomic Energy Research (AER) for Investigating Neutron Physics and Thermohydraulics Problems of Reactor Safety, Paks, Hungary, September 21–26, 1992, p. 389, KFKI Atomic Energy Research Institute (1992).
   Google Scholar
• F. J. TURINSKY, H. N. SAROUR, R. M. K. ALCHALABI, P. ENGRAND, F. X. FAURE, and W. GUO, “NESTLE 5.02, Code System to Solve the Few-Group Neutron Diffusion Equation for Fixed-Source Steady-State and Transient Problems,” CCC-641, Radiation Shielding Information Center (1996).
   Google Scholar
• T. BEAM, K. IVANOV, B. TAYLOR, and A. BARATTA, “PWR MSLB Benchmark. Volume II: Results of Phase 1 on Point Kinetics,” NEA/NSC/DOC(2000)21, Nuclear Energy Agency Nuclear Science Committee.
   Google Scholar