DOI QR코드

DOI QR Code

Comprehensive investigation of the Ronen method in slab geometry

  • Roy Gross (The Unit of Nuclear Engineering, Ben-Gurion University of the Negev) ;
  • Johan Cufe (The Unit of Nuclear Engineering, Ben-Gurion University of the Negev) ;
  • Daniele Tomatis (Universite Paris-Saclay, CEA, DES, Service d'etudes des reacteurs et de mathematiques appliquees (SERMA)) ;
  • Erez Gilad (The Unit of Nuclear Engineering, Ben-Gurion University of the Negev)
  • Received : 2022.07.16
  • Accepted : 2022.09.24
  • Published : 2023.02.25

Abstract

A comprehensive investigation of the Ronen method is performed in homogeneous and heterogeneous slab problems from the Sood benchmark, considering isotropic and linearly-anisotropic problems. Three finite differences implementations are exercised and compared. The results are compared to reference solutions using one and two energy groups. The validation is performed for the criticality eigenvalue and the fundamental neutron flux distribution. The results demonstrate the significantly improved accuracy achievable by the Ronen method using a broad set of problems. For standard convergence tolerances, the maximal deviation in criticality eigenvalue is less than ten pcm, and the maximal deviation in the spatial distribution of the flux is less than 2%, always located near sharp interfaces or vacuum boundaries.

Keywords

Acknowledgement

RG thanks the Israel Ministry of Energy for its support as part of the scholarship program for undergraduate and graduate students in energy-related fields, contract no. 219-11-045. JC thanks FRAMATOME for its support as part of a collaboration agreement regarding this research.

References

  1. Y. Ronen, Accurate relations between the neutron current densities and the neutron fluxes, Nucl. Sci. Eng. 146 (2) (2004) 245-247.  https://doi.org/10.13182/NSE04-A2407
  2. D. Tomatis, A. Dall'Osso, Application of a numerical transport correction in diffusion calculations, in: Int. Conf. on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2011), Rio de Janeiro, RJ, Brazil, May 8-12, 2011, 05 2011. 
  3. Daniele Tomatis, Roy Gross, Erez Gilad, On the ronen method in simple 1-D geometries for neutron transport theory solutions, J. Comput. Theor. Trans. 50 (2) (2021) 134-157.  https://doi.org/10.1080/23324309.2020.1843496
  4. Roy Gross, Daniele Tomatis, Erez Gilad, High-accuracy neutron diffusion calculations based on integral transport theory, Eur. Phys. J. Plus 135 (2) (2020) 235. 
  5. Kord S. Smith, Nodal method storage reduction by nonlinear iteration, Trans. Am. Nucl. Soc. 44 (1983) 265-266. 
  6. Nicholas C. Henderson, Ravi Varadhan, Damped anderson acceleration with restarts and monotonicity control for accelerating em and em-like algorithms, J. Computational Graphical Stat. 28 (4) (2019) 834-846.  https://doi.org/10.1080/10618600.2019.1594835
  7. Homer F. Walker, Peng Ni, Anderson acceleration for fixed-point iterations, SIAM J. Numer. Anal. 49 (4) (2011) 1715-1735.  https://doi.org/10.1137/10078356X
  8. Avneet Sood, R. Arthor Forster, D. Kent Parsons, Analytical benchmark test set for criticality code verification, Prog. Nucl. Energy 42 (1) (2003) 55-106.  https://doi.org/10.1016/S0149-1970(02)00098-7
  9. Milton Abramowitz, Irene A. Stegun, Handbook of mathematical functions with formulas, graphs, and mathematical tables, Dover Publications New York, 1972. 
  10. Nam Zin Cho, Gil Soo Lee, Comparison of cmfd and p-cmfd acceleration methods for neutron transport calculations, Proc. Korean Nucl. Soc. Gyeongju, Korea (2003) 53.1. 
  11. E.E. Lewis, W.F. Miller, Computational Methods of Neutron Transport, John Wiley and Sons, Inc, New York, NY, La Grange Park, Ill., USA, 1984. 
  12. W.M. Stacey, Nuclear Reactor Physics, John Wiley & Sons, 2007. 
  13. J.R. Lamarsh, Introduction to Nuclear Reactor Theory, Addison-Wesley, Reading, Mass, 1966. 
  14. J.J. Duderstadt, L.J. Hamilton, Nuclear Reactor Analysis, Wiley, 1976. 
  15. M. Jarrett, et al., Analysis of stabilization techniques for CMFD acceleration of neutron transport problems, Nucl. Sci. Eng. 184 (2) (2016) 208-227.  https://doi.org/10.13182/NSE16-51
  16. A. Zhu, et al., An optimally diffusive coarse mesh finite difference method to accelerate neutron transport calculations, Ann. Nucl. Energy 95 (2016) 116-124.  https://doi.org/10.1016/j.anucene.2016.05.004
  17. Junzi Zhang, Brendan O'Donoghue, Stephen Boyd, Globally convergent type-I Anderson acceleration for nonsmooth fixed-point iterations, SIAM J. Optimization 30 (4) (2020) 3170-3197.  https://doi.org/10.1137/18M1232772
  18. Ansar Calloo, Le Tellier, Romain, Couyras, David, Comparison of Chebyshev and Anderson accelerations for the neutron transport equation, EPJ Web Conf. 247 (2021), 03001.