Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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OECD/NEA BENCHMARK FOR UNCERTAINTY ANALYSIS IN MODELING (UAM) FOR LWRS - SUMMARY AND DISCUSSION OF NEUTRONICS CASES (PHASE I)

  • Bratton, Ryan N. (The Pennsylvania State University, Department of Mechanical and Nuclear Engineering) ;
  • Avramova, M. (The Pennsylvania State University, Department of Mechanical and Nuclear Engineering) ;
  • Ivanov, K. (The Pennsylvania State University, Department of Mechanical and Nuclear Engineering)
  • Received : 2013.12.28
  • Published : 2014.06.25
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Abstract

A Nuclear Energy Agency (NEA), Organization for Economic Co-operation and Development (OECD) benchmark for Uncertainty Analysis in Modeling (UAM) is defined in order to facilitate the development and validation of available uncertainty analysis and sensitivity analysis methods for best-estimate Light water Reactor (LWR) design and safety calculations. The benchmark has been named the OECD/NEA UAM-LWR benchmark, and has been divided into three phases each of which focuses on a different portion of the uncertainty propagation in LWR multi-physics and multi-scale analysis. Several different reactor cases are modeled at various phases of a reactor calculation. This paper discusses Phase I, known as the "Neutronics Phase", which is devoted mostly to the propagation of nuclear data (cross-section) uncertainty throughout steady-state stand-alone neutronics core calculations. Three reactor systems (for which design, operation and measured data are available) are rigorously studied in this benchmark: Peach Bottom Unit 2 BWR, Three Mile Island Unit 1 PWR, and VVER-1000 Kozloduy-6/Kalinin-3. Additional measured data is analyzed such as the KRITZ LEU criticality experiments and the SNEAK-7A and 7B experiments of the Karlsruhe Fast Critical Facility. Analyzed results include the top five neutron-nuclide reactions, which contribute the most to the prediction uncertainty in keff, as well as the uncertainty in key parameters of neutronics analysis such as microscopic and macroscopic cross-sections, six-group decay constants, assembly discontinuity factors, and axial and radial core power distributions. Conclusions are drawn regarding where further studies should be done to reduce uncertainties in key nuclide reaction uncertainties (i.e.: $^{238}U$ radiative capture and inelastic scattering (n, n') as well as the average number of neutrons released per fission event of $^{239}Pu$).

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References

  1. K. Ivanov, M. Avramova, S. Kamerow, I. Kodeli, E. Sartori, E. Ivanov, and O. Cabellos, "Benchmark for Uncertainty Analysis in Modelling (UAM) for the Design, Operation and Safety Analysis of LWRs," NEA/NSC/DOC(2013)7, Nuclear Energy Agency (2013).
  2. M. A. Jessee, P. J. Turinsky, and H. S. Abdel-Khalik, "Many-Group Cross-Section Adjustment Techniques for Boiling Water Reactor Adaptive Simulation," Nuclear Science and Engineering, vol. 169, pp. 40-55 (2011). https://doi.org/10.13182/NSE09-67
  3. A. J. Koning and D. Rochman, TENDL-2008: Consistent TALYS-base Evaluated Nuclear Data Library including covariance data, www.talys.eu/tendl-2008, OECD/NEA JEF/DOC-1262 (2005).
  4. M. L. Williams, D. Wiarda, G. Arbanas, and B. L. Broadhead, "SCALE Nuclear Data Covariance Library," Sect. M19 in SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluations, ORNL/TM-2005/39, Version 6.1, Oak Ridge National Laboratory (2011).
  5. J. Solis, K. Ivanov, B. Sarikaya, A. Olson, and K. Hunt, "BWR TT Benchmark. Volume I: Final Specifications", NEA/NSC/DOC(2001)1, Nuclear Energy Agency (2001).
  6. K. Ivanov, T. Beam, A. Baratta, A. Irani, and N. Trikouros, "PWR MSLB Benchmark. Volume 1: Final Specifications", NEA/NSC/DOC(99)8, Nuclear Energy Agency (1999).
  7. B. Ivanov, K. Ivanov, P. Groudev, M. Pavlova, and V. Hadjiev, "VVER-1000 Coolant Transient Benchmark (V1 000-CT). Phase 1 - Final Specification". NEA/NSC/DOC (2002)6, Nuclear Energy Agency (2002).
  8. C. Vaglio and A. Santamarina "Assembly and Core Specification of Generation 3 PWR", October 2010, CEA, France.
  9. T. Horiuchi et al. "Error Decomposition of Approximations for BWR Core Calculations", Proc. Int. Conf. New Frontiers of Nuclear Technology. Reactor Physics (PHYSOR 2002), Seoul, South Korea, Oct. 7-10, 2002.
  10. "Benchmark on the KRITZ-2 LEU and MOX Critical Experiments - Final Report", NEA/NSC/DOC(2005)24, ISBN 92-64-02298-8, Nuclear Energy Agency (2005).
  11. International Reactor Physics Experiments Database Project (IRPhE), "International Handbook of Evaluated Reactor Physics Benchmark Experiments", NEA/NSC/DOC (2006)1, Nuclear Energy Agency (2009).
  12. EPRI NP-240 (1976), "Core Design and Operating Data for Cycles 1 and 2of Quad Cities 1".
  13. A. Karve et al. "Uncertainty Estimates in Cold Critical Eigenvalue Predictions", Proc. of ANFM-2003 Conference, Hilton Head Island, South Carolina, USA (2003).
  14. International Handbook of Evaluated Criticality Benchmark Experiments, "International Handbook of Evaluated Reactor Physics Benchmark Experiments", NEA/NSC/DOC (95)03, Nuclear Energy Agency (2007).
  15. S. Baker, "TransLAT Lattice Physics Code Benchmark to B&W Gadolinia Criticals", Proc. Int. Conf. New Frontiers of Nuclear Technology. Reactor Physics (PHYSOR 2004), Chicago, USA (2004).
  16. E. Ivanov, V. Mastrangelo, A. Duranti, and I. Kodeli, "Specification of Kinetic Parameters Benchmark SNEAK", January 2011, France.
  17. I. Kodeli, "Sensitivity and Uncertainty in the Effective Delayed Neutron Fraction (${\beta}_{eff}$)" Proc. Int. Conf. Advances in Reactor Physics (PHYSOR 2012), Knoxville, USA, April 15-20 (2012).
  18. T. Endo, K. Ohori, A. Yamamoto, "Application of the Robust Design Concept for Fuel Loading Pattern," J. Nucl. Sci. Technol., 48, pp.1077-1086 (2011). https://doi.org/10.1080/18811248.2011.9711792

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