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Verification of multilevel octree grid algorithm of SN transport calculation with the Balakovo-3 VVER-1000 neutron dosimetry benchmark

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초록

Neutron transport calculations are extremely challenging due to the high computational cost of large and complex problems. A multilevel octree grid algorithm (MLTG) of discrete ordinates method was developed to improve the modeling accuracy and simulation efficiency on 3-D Cartesian grids. The Balakovo-3 VVER-1000 neutron dosimetry benchmark is calculated to verify and validate this numerical technique. A simplified S2 synthetic acceleration is used in the MLTG calculation method to improve the convergence of the source iterations. For the triangularly arranged fuel pins, we adopt a source projection algorithm to generate pin-by-pin source distributions of hexagonal assemblies. MLTG provides accurate geometric modeling and flexible fixed source description at a lower cost than traditional Cartesian grids. The total number of meshes is reduced to 1.9 million from the initial 9.5 million for the Balakovo-3 model. The numerical comparisons show that the MLTG results are in satisfactory agreement with the conventional SN method and experimental data, within the root-mean-square errors of about 4% and 10%, respectively. Compared to uniform fine meshing, approximately 70% of the computational cost can be saved using the MLTG algorithm for the Balakovo-3 computational model.

Abstract

Neutron transport calculations are extremely challenging due to the high computational cost of large and complex problems. A multilevel octree grid algorithm (MLTG) of discrete ordinates method was developed to improve the modeling accuracy and simulation efficiency on 3-D Cartesian grids. The Balakovo-3 VVER-1000 neutron dosimetry benchmark is calculated to verify and validate this numerical technique. A simplified S2 synthetic acceleration is used in the MLTG calculation method to improve the convergence of the source iterations. For the triangularly arranged fuel pins, we adopt a source projection algorithm to generate pin-by-pin source distributions of hexagonal assemblies. MLTG provides accurate geometric modeling and flexible fixed source description at a lower cost than traditional Cartesian grids. The total number of meshes is reduced to 1.9 million from the initial 9.5 million for the Balakovo-3 model. The numerical comparisons show that the MLTG results are in satisfactory agreement with the conventional SN method and experimental data, within the root-mean-square errors of about 4% and 10%, respectively. Compared to uniform fine meshing, approximately 70% of the computational cost can be saved using the MLTG algorithm for the Balakovo-3 computational model.

참고문헌 (39)

  1. Paul K. Romano, "OpenMC: A state-of-the-art Monte Carlo code for research and development", Annals of Nuclear Energy, 82, pp.90~97 (2015), Elsevier BV[DOI]
  2. Jaakko Leppänen, "The Serpent Monte Carlo code: Status, development and applications in 2013", Annals of Nuclear Energy, 82, pp.142~150 (2015), Elsevier BV[DOI]
  3. RICHARD SANCHEZ, "PROSPECTS IN DETERMINISTIC THREE-DIMENSIONAL WHOLE-CORE TRANSPORT CALCULATIONS", Nuclear Engineering and Technology, 44(2), pp.113~150 (2012), 한국원자력학회
  4. Thomas M. Evans, "Denovo: A New Three-Dimensional Parallel Discrete Ordinates Code in SCALE", Nuclear Technology, 171(2), pp.171~200 (2010), Informa UK Limited[DOI]
  5. William Boyd, "The OpenMOC method of characteristics neutral particle transport code", Annals of Nuclear Energy, 68, pp.43~52 (2014), Elsevier BV[DOI]
  6. Derek R. Gaston, "Method of Characteristics for 3D, Full-Core Neutron Transport on Unstructured Mesh", Nuclear Technology, 207(7), pp.931~953 (2021), Informa UK Limited[DOI]
  7. Todd A. Wareing, "Discontinuous Finite Element<i>S<sub>N<", sub><, Nuclear Science and Engineering, pp.2001, 138(3)[DOI]
  8. A.R. Owens, "Discontinuous isogeometric analysis methods for the first-order form of the neutron transport equation with discrete ordinate (S) angular discretisation", Journal of Computational Physics, 315, pp.501~535 (2016), Elsevier BV[DOI]
  9. Petri Kotiluoto, "Fast tree multigrid transport application for the simplified P3approximation", Nuclear Science and Engineering, 138(3), pp.269~278 (2001), Informa UK Limited[DOI]
  10. Emiliano Masiello, "3D heterogeneous Cartesian cells for transport-based core simulations", Annals of Nuclear Energy, 142, pp.107364~ (2020), Elsevier BV[DOI]
  11. Katherine E. Royston, "Application of the Denovo Discrete Ordinates Radiation Transport Code to Large-Scale Fusion Neutronics", Fusion Science and Technology, 74(4), pp.303~314 (2018), Informa UK Limited[DOI]
  12. Roberto Orsi, "H.B. Robinson-2 pressure vessel dosimetry benchmark: Deterministic three-dimensional analysis with the TORT transport code", Nuclear Engineering and Technology, 52(2), pp.448~455 (2020), 한국원자력학회
  13. Longfei Xu, "Study of the PWR ex-core detector response simulation based on the 3D S method", Annals of Nuclear Energy, 139, pp.107223~ (2020), Elsevier BV[DOI]
  14. S.A. Turner, "Automatic mesh coarsening for discrete ordinates codes", International Conference on Mathematics and Computations (M&C '99) (1999)
  15. Randal S. Baker, "A Block Adaptive Mesh Refinement Algorithm for the Neutral Particle Transport Equation", Nuclear Science and Engineering, 141(1), pp.1~12 (2002), Informa UK Limited[DOI]
  16. A. Haghighat, "Effectiveness of pentran™'s unique numerics for simulation of the Kobayashi benchmarks", Progress in Nuclear Energy, 39(2), pp.191~206 (2001), Elsevier BV[DOI]
  17. Jose I. Duo, "A posteriori error estimator and AMR for discrete ordinates nodal transport methods", Annals of Nuclear Energy, 36(3), pp.268~273 (2009), Elsevier BV[DOI]
  18. D. Fournier, "Improvement of neutronic calculations on a MASURCA core using adaptive mesh refinement capabilities", International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2011) (2011)
  19. Michael W. Hackemack, "Quadratic serendipity discontinuous finite element discretization for S transport on arbitrary polygonal grids", Journal of Computational Physics, 374, pp.188~212 (2018), Elsevier BV[DOI]
  20. Cong Liu, "Multilevel mesh adaptivity for discrete ordinates transport calculation with spatial-moment-ratio indicators", Annals of Nuclear Energy, 176, pp.109288~ (2022), Elsevier BV[DOI]
  21. Cong Liu, "Nonmatching Discontinuous Cartesian Grid Algorithm Based on the Multilevel Octree Architecture for Discrete Ordinates Transport Calculation", Nuclear Science and Engineering, 194(12), pp.1175~1201 (2020), Informa UK Limited[DOI]
  22. Balakovo-3 VVER-1000 exvessel neutron dosimetry benchmark experiment, SINBAD Project Report, "G. Borodkin", Scientific and Engineering Centre for Nuclear and Radiation Safety (SEC NRS)and Forschungszentrum Rossendorfe.V. (FZR), ~ (2002)
  23. G. Borodkin, "Balakovo-3 ex-vessel exercise:analysis of calculation results intercomparison and comparison with reference data", Proceedings of the 11th International Symposium on Reactor Dosimetry, pp.665~673 (2003)
  24. Ivan A. Kodeli, "SINBAD – Radiation shielding benchmark experiments", Annals of Nuclear Energy, 159, pp.108254~ (2021), Elsevier BV[DOI]
  25. Jong Oh Kim, "A new uncertainty arising in reactor pressure vessel fluence calculation", Annals of Nuclear Energy, 25(12), pp.963~982 (1998), Elsevier BV[DOI]
  26. Alexander Vasiliev, "Development of a CASMO-4", SIMULATE-3, Annals of Nuclear Energy, pp.2007, 34(8)[DOI]
  27. G.E. Sjoden, "The exponential directional weighted (EDW) Sn differencing scheme in 3-D Cartesian geometry", Joint International Conference on Mathematical Methods and Supercomputing for Nuclear Applications (1997)
  28. Cong Liu, "Solution-dependent predictor-corrector flux mapping algorithm for discrete ordinates calculation on multilevel discontinuous grids", Annals of Nuclear Energy, 152, pp.108033~ (2021), Elsevier BV[DOI]
  29. J. I. Duo, "Spatial Convergence Study of Discrete Ordinates Methods Via the Singular Characteristic Tracking Algorithm", Nuclear Science and Engineering, 162(1), pp.41~55 (2009), Informa UK Limited[DOI]
  30. Kirk A. Mathews, "On the Propagation of Rays in Discrete Ordinates", Nuclear Science and Engineering, 132(2), pp.155~180 (1999), Informa UK Limited[DOI]
  31. Gilles L. Ramone, "A Transport Synthetic Acceleration Method for Transport Iterations", Nuclear Science and Engineering, 125(3), pp.257~283 (1997), Informa UK Limited[DOI]
  32. Marvin L. Adams, "Fast iterative methods for discrete-ordinates particle transport calculations", Progress in Nuclear Energy, 40(1), pp.3~159 (2002), Elsevier BV[DOI]
  33. Alireza Haghighat, "Evaluation of the Uncertainties in the Source Distribution for Pressure Vessel Neutron Fluence Calculations", Nuclear Technology, 109(1), pp.54~75 (1995), Informa UK Limited[DOI]
  34. 김도헌, "Validation of an ENDF", B-VII.0-Based Neutron and Photon Shielding Library in MATXS-Format, 2011, pp.59(23), 1199~1202[DOI]
  35. Summary Description of the New International Reactor Dosimetry and Fusion File (IRDFF Release 1.0), "E. M. Zsolnay", International Atomic Energy Agency, ~ (2012)
  36. U.S. Nuclear Regulatory Commission, "Calculational and dosimetry methods for determining pressure vessel neutron fluence, Regulatory Guide 1", 190~ (2001)
  37. R. E. Maerker, "Accounting for Changing Source Distributions in Light Water Reactor Surveillance Dosimetry Analysis", Nuclear Science and Engineering, 94(4), pp.291~308 (1986), Informa UK Limited[DOI]
  38. H.B. Robinson-2 Pressure Vessel Benchmark, "I. Remec", Oak Ridge National Laboratory, ~, pp.ORNL (1998), TM-13204
  39. Yixue Chen, "ARES: A Parallel Discrete Ordinates Transport Code for Radiation Shielding Applications and Reactor Physics Analysis", Science and Technology of Nuclear Installations, 2017, pp.1~11 (2017), Hindawi Limited[DOI]

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