Skip to main content
Log in

A multithreaded parallel upwind sweep algorithm for the SN transport equations discretized with discontinuous finite elements

  • Published:
Nuclear Science and Techniques Aims and scope Submit manuscript

Abstract

The complex structure and strong heterogeneity of advanced nuclear reactor systems pose challenges for high-fidelity neutron-shielding calculations. Unstructured meshes exhibit strong geometric adaptability and can overcome the deficiencies of conventionally structured meshes in complex geometry modeling. A multithreaded parallel upwind sweep algorithm for SN transport was proposed to achieve a more accurate geometric description and improve the computational efficiency. The spatial variables were discretized using the standard discontinuous Galerkin finite-element method. The angular flux transmission between neighboring meshes was handled using an upwind scheme. In addition, a combination of a mesh transport sweep and angular iterations was realized using a multithreaded parallel technique. The algorithm was implemented in the 2D/3D SN transport code ThorSNIPE, and numerical evaluations were conducted using three typical benchmark problems: IAEA, Kobayashi-3i, and VENUS-3. These numerical results indicate that the multithreaded parallel upwind sweep algorithm can achieve high computational efficiency. ThorSNIPE, with a multithreaded parallel upwind sweep algorithm, has good reliability, stability, and high efficiency, making it suitable for complex shielding calculations.

This is a preview of subscription content, log in via an institution to check access.

Access this article

Price excludes VAT (USA)
Tax calculation will be finalised during checkout.

Instant access to the full article PDF.

Fig. 1
Fig. 2
Fig. 3
Fig. 4
Fig. 5
Fig. 6
Fig. 7
Fig. 8
Fig. 9
Fig. 10
Fig. 11

Similar content being viewed by others

Data availability

The data that support the findings of this study are openly available in Science Data Bank at https://doi.org/10.57760/sciencedb.13607 and https://cstr.cn/31253.11.sciencedb.13607.

References

  1. E.E. Lewis, W.F. Miller, Computational Methods of Neutron Transport (American Nuclear Society, Illinois, 1981)

    Google Scholar 

  2. W.A. Rhoades, W.W. Engle Jr., New Weighted-Difference Formulation for Discrete-Ordinates Calculations. Tech. Rep., Oak Ridge National Laboratory, CONF-771109-53 (1977)

  3. Y. Chen, B. Zhang, L. Zhang et al., ARES: a parallel discrete ordinates transport code for radiation shielding applications and reactor physics analysis. Sci. Tech. Nucl. Install. 2017, 2596727 (2017). https://doi.org/10.1155/2017/2596727

    Article  Google Scholar 

  4. T. Cheng, L. Wei, B. Zhone et al., Reconstruction and parallelization of 3D SN program for neutron/photon transport. Nucl. Power Eng. 35, 147–150 (2014). https://doi.org/10.13832/j.jnpe.2014.S2.0147

    Article  Google Scholar 

  5. M.A. Puso, J. Solberg, A stabilized nodally integrated tetrahedral. Int. J. Numer. Methods Eng. 67, 841–867 (2006). https://doi.org/10.1002/nme.1651

    Article  MathSciNet  Google Scholar 

  6. Y. Wang, J.C. Ragusa, Standard and goal-oriented adaptive mesh refinement applied to radiation transport on 2D unstructured triangular meshes. J. Comput. Phys. 230, 763–788 (2011). https://doi.org/10.1016/j.jcp.2010.10.018

    Article  ADS  MathSciNet  Google Scholar 

  7. N. Dai, B. Zhang, Y. Chen et al., Adaptive discontinuous finite element quadrature sets over an icosahedron for discrete ordinates method. Nucl. Sci. Tech. 32, 98 (2021). https://doi.org/10.1007/s41365-021-00934-7V

    Article  Google Scholar 

  8. V. Labouré, Y. Wang, J. Ortensi et al., Multischeme equivalence procedure for neutron transport finite element methods. Ann. Nucl. Energ. 166, 108712 (2022). https://doi.org/10.1016/j.anucene.2021.108712

    Article  Google Scholar 

  9. B.Q. Li, Discontinuous Finite Elements in Fluid Dynamics and Heat Transfer (Springer, London, 2006)

    Book  Google Scholar 

  10. D. Kuzmin, A Guide to Numerical Methods for Transport Equations (Thesis, University of Erlangen-Nuremberg, 2010)

  11. H. Guo, W. Chen, X. Jiang et al., A new continuous finite element SN method for solving first-order neutron transport equation. Ann. Nucl. Energ. 175, 109237 (2022). https://doi.org/10.1016/j.anucene.2022.109237

    Article  Google Scholar 

  12. C.C. Pain, M.D. Eaton, R.P. Smedley-Stevenson et al., Streamline upwind Petrov–Galerkin methods for the steady-state Boltzmann transport equation. Comput. Methods Appl. Mech. Eng. 195, 4448–4472 (2006). https://doi.org/10.1016/j.cma.2005.09.004

    Article  ADS  Google Scholar 

  13. T.A. Manteuffel, K.J. Ressel, Least-squares finite-element solution of the neutron transport equation in diffusive regimes. SIAM J. Numer. Anal. 35, 806–835 (1998). https://doi.org/10.1137/S003614299629970

    Article  MathSciNet  Google Scholar 

  14. W.H. Reed, T.R. Hill, Triangular Mesh Methods for the Neutron Transport Equation. Tech. Rep., Los Alamos National Laboratory, LA-UR-73-479 (1973)

  15. O.C. Zienkiewicz, R.L. Taylor, J.Z. Zhu, The Finite Element Method: Its Basis and Fundamentals, 6th edn. (Elsevier, Butterworth Heinemann, Oxford, 2005), pp.14–17

    Google Scholar 

  16. Y. Wang, S. Schunert, J. Ortensi et al., Rattlesnake: a MOOSE-based multiphysics multischeme radiation transport application. Nucl. Technol. 207, 1047–1072 (2021). https://doi.org/10.1080/00295450.2020.1843348

    Article  ADS  Google Scholar 

  17. S. Plimpton, B. Hendrickson, S. Burns et al., Parallel algorithms for radiation transport on unstructured grids. in Proceedings of the 2000 ACM/IEEE Conference (Dallas, Texas, USA, 2000). https://doi.org/10.1109/SC.2000.10030

  18. S.D. Pautz, An algorithm for parallel SN sweeps on unstructured meshes. Nucl. Sci. Eng. 140, 11–136 (2002)

    Article  ADS  Google Scholar 

  19. J.Y. Moller, J.J. Lautard, Minaret, a deterministic neutron transport solver for nuclear core calculations. in International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (Rio de Janeiro, Brazil, 2011)

  20. W.K. Jong, O.L. Young, A deep penetration problem calculation using AETIUS: an easy modeling discrete ordinates transport code using unstructured tetrahedral mesh, shared memory parallel. EPJ Web Conf. 153, 06025 (2017). https://doi.org/10.1051/epjconf/201715306025

    Article  Google Scholar 

  21. Z. Zong, M. Cheng, A two-dimensional finite element shielding calculation code with mass-matrix lumping technique and unstructured meshes. Nucl. Tech. 46, 020602 (2023). https://doi.org/10.11889/j.0253-3219.2023.hjs.46.020602. (in Chinese)

    Article  Google Scholar 

  22. D. Arndt, W. Bangerth, M. Feder et al., The deal. II library, version 9.4. J. Numer. Math. 30, 231–246 (2022). https://doi.org/10.1515/jnma-2022-0054

    Article  MathSciNet  Google Scholar 

  23. V. Labouré, R.G. McClarren, Y. Wang, Globally conservative, hybrid self-adjoint angular flux and least-squares method compatible with voids. Nucl. Sci. Eng. 185, 294–306 (2017). https://doi.org/10.1080/00295639.2016.1272374

    Article  ADS  Google Scholar 

  24. Y.Y. Azmy, Performance and performance modeling of a parallel algorithm for solving the neutron transport equation. J. Supercomput. 6, 211–235 (1992). https://doi.org/10.1007/BF00155800

    Article  Google Scholar 

  25. G. Zhang, J. Liu, L. Cao et al., Neutronic calculations of the China dual-functional lithium–lead test blanket module with the parallel discrete ordinates code hydra. Nucl. Sci. Tech. 31, 74 (2020). https://doi.org/10.1007/s41365-020-00789-4

    Article  Google Scholar 

  26. Z. Hong, G. Yuan, A parallel algorithm with interface prediction and correction for spherical geometric transport equation. Prog. Nucl. Energ. 51, 268–273 (2009). https://doi.org/10.1016/j.pnucene.2008.09.003

    Article  Google Scholar 

  27. J.W. Fisher, Y.Y. Azmy, Comparison via parallel performance models of angular and spatial domain decompositions for solving neutral particle transport problems. Prog. Nucl. Energ. 47, 37–60 (2007). https://doi.org/10.1016/j.pnucene.2006.08.003

    Article  Google Scholar 

  28. Y.Y. Azmy, On the adequacy of message-passing parallel supercomputers for solving neutron transport problems. in Proceedings of the 1991 ACM/IEEE Conference on Supercomputing (New York, USA, 12–16 November 1991). https://doi.org/10.1109/SUPERC.1990.130088

  29. V. Alessandrini, Shared Memory Application Programming Concepts and Strategies in Multicore Application Programming (Morgan Kaufmann, Boston, 2015), pp.307–339

    Google Scholar 

  30. J. Stepanek, T. Auerbach, W. Hälg, Calculation of Four Thermal Reactor Benchmark Problems in X-Y Geometry. Tech. Rep. ANS, USA, EIR-464 (1982)

  31. K. Kobayashi, N. Sugimura, Y. Nagaya, 3D radiation transport benchmark problems and results for simple geometries with void region. Prog. Nucl. Energ. 39, 119–144 (2001). https://doi.org/10.1016/S0149-1970(01)00007-5

    Article  Google Scholar 

  32. M. Pescarini, R. Orisi, M. G. Borgia et al., ENEA Nuclear Data Center Neutron Transport Analysis of the VENUS-3 Shielding Benchmark Experiment. Tech. Rep. ENEA-Bologna, Italy, KT-SCG-00013 (2001)

  33. D.H. Kim, C.S. Gil, Y.O. Lee, Validation of an ENDF/B-VII.0-based neutron and photon shielding library in MATXS-format. J. Korean Phys. Soc. 59, 1199–1202 (2011). https://doi.org/10.3938/jkps.59.1199

    Article  ADS  Google Scholar 

Download references

Author information

Authors and Affiliations

Authors

Contributions

All authors contributed to the study conception and design. Material preparation, data collection, and analysis were performed by Zhi-Wei Zong and Mao-Song Cheng. The first draft of the manuscript was written by Zhi-Wei Zong and all authors commented on previous versions of the manuscript. All authors read and approved the final manuscript.

Corresponding author

Correspondence to Mao-Song Cheng.

Ethics declarations

Conflict of interest

The authors declare that they have no competing interests.

Additional information

This work was supported by the Strategic Pilot Science and Technology Project of the Chinese Academy of Sciences.

Rights and permissions

Springer Nature or its licensor (e.g. a society or other partner) holds exclusive rights to this article under a publishing agreement with the author(s) or other rightsholder(s); author self-archiving of the accepted manuscript version of this article is solely governed by the terms of such publishing agreement and applicable law.

Reprints and permissions

About this article

Check for updates. Verify currency and authenticity via CrossMark

Cite this article

Zong, ZW., Cheng, MS., Yu, YC. et al. A multithreaded parallel upwind sweep algorithm for the SN transport equations discretized with discontinuous finite elements. NUCL SCI TECH 34, 200 (2023). https://doi.org/10.1007/s41365-023-01355-4

Download citation

  • Received:

  • Revised:

  • Accepted:

  • Published:

  • DOI: https://doi.org/10.1007/s41365-023-01355-4

Keywords

Navigation