Nuclear Engineering and Technology

  • 제56권10호
  • /
  • Pages.4195-4206
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  • 2024
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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VINUS: A neutron transport solver based on the variational nodal method for reactor core analysis

  • Zhulun Li (School of Nuclear Science and Engineering, North China Electric Power University) ;
  • Xubo Ma (School of Nuclear Science and Engineering, North China Electric Power University) ;
  • Longxiao Ma (School of Nuclear Science and Engineering, North China Electric Power University) ;
  • Teng Zhang (School of Nuclear Science and Engineering, North China Electric Power University) ;
  • Zhirui Du (School of Nuclear Science and Engineering, North China Electric Power University)
  • 투고 : 2024.02.27
  • 심사 : 2024.05.21
  • 발행 : 2024.10.25
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초록

Compared to traditional transverse integration methods, the variational nodal method, with its unique advantages, is more suitable for high-fidelity calculations of reactor physics in reactors with complex geometries and finer detail descriptions. In this study, the basic theory of the variational nodal method was derived and the VINUS code is developed. The neutron solver based on this method is adaptable to various geometric models, and showcased the code's fundamental framework. On this basis, a set of self-designed macroscopic cross-section benchmarks, actual macroscopic cross-section benchmark VVER-440, and few-group microscopic cross-section benchmark RBEC-M for fast spectrum reactors were used to verify different functionalities of VINUS. The results were shown that VINUS code maintains good computational accuracy and convergence trends. For the VVER-440 benchmarks, the deviation of keff of VINUS from reference is less than 100 pcm, and the maximum power deviation is less than 4 %. For the RBEC-M, the deviation of keff is 125 pcm, and the maximum power deviation is less than 5 %. These outcomes collectively demonstrate the solver's potential for engineering applications in future advanced reactor designs.

키워드

과제정보

This study was supported by the National Natural Science Foundation of China (No.11875128).

참고문헌

  1. G. Palmiotti, E.E. Lewis, C.B. Carrico, VARIANT: VARIational Anisotropic Nodal Transport for Multidimensional Cartesian and Hexagonal Geometry Calculation, Argonne National Laboratory, October, 1995, pp. 1-146.
  2. I. Dilber, E.E. Lewis, Two dimensional variational coarse mesh methods, Proc. Topl. Mtg. Reactor Physics and Shielding (1984) 17-19.
  3. R.D. Lawrence, The DIF3D Nodal Neutronics Option for Two- and Three-Dimensional Diffusion Theory Calculations in Hexagonal Geometry, Technology, 1983. March 1983.
  4. M.A. Smith, E.E. Lewis, E.R. Shemon, DIF3D-VARIANT 11.0: A Decade of Updates, Argonne National Laboratory, 2014. http://www.osti.gov/servlets/purl/1127298/.
  5. J.Y. Doriath, J.M. Ruggieri, G. Buzzi, J.M. Rieunier, P. Smith, P. Fougeras, A. Maghnouj, Reactor analysis using a variational nodal method implemented in the ERANOS system, Proc. Topl. Mtg. Advances in Reactor Physics (1994) 11-15.
  6. Y. Wang, C. Rabiti, G. Palmiotti, Krylov solvers preconditioned with the low-order red-black algorithm for the pn hybrid fem for the instant code, International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C2011) (2011).
  7. T. Zhang, W. Xiao, H. Yin, Q. Sun, X. Liu, VITAS: a multi-purpose simulation code for the solution of neutron transport problems based on variational nodal methods, Ann. Nucl. Energy 178 (2022) (2022) 109335, https://doi.org/10.1016/j.anucene.2022.109335.
  8. Y. Li, Advanced Reactor Core Neutronics Computational Algorithms Based on the Variational Nodal and Nodal SP3 Methods, Xi'an Jiaotong University, 2012 (in Chinese).
  9. K.F. Laurin-Kovitz, E.E. Lewis, Variational nodal transport perturbation theory, Nucl. Sci. Eng. 123 (3) (1996) 369-380, https://doi.org/10.13182/NSE96-A24200.
  10. M.A. Smith, Three-dimensional Nodal Neutron Transport Program with the Ability to Handle Spatial Heterogeneities, University of Missouri-Rolla, 2001.
  11. E.E. Lewis, C.B. Carrico, G. Palmiotti, Variational nodal formulation for the spherical harmonics equations, Nucl. Sci. Eng. 122 (2) (1996) 194-203, https://doi.org/10.13182/NSE96-1.
  12. E.E. Lewis, W.F. Miller, Computational methods of neutron transport. https://www.osti.gov/biblio/5538794, 1984.
  13. G.E. Bonney, G.E. Kissling, Gram-schmidt 0rthogonalization of multinormal variates:applications in genetics, Biom. J. 28 (4) (1986) 417-425.
  14. Z. Xie, L. Deng, Numerical Calculation Method of Neutron Transport Theory, Xi'an Jiaotong University Press, 2022 (in Chinese).
  15. W. Xia, Research on Variational Integral Transport Nodal Method and Fast Solving Algorithm, Shanghai Jiao Tong University, 2020 (in Chinese).
  16. E.E. Lewis, M.A. Smith, N. Tsoulfanidis, G. Palmiotti, T.A. Taiwo, R.N. Blomquist, Benchmark Specification for Deterministic 2-D/3-D MOX Fuel Assembly Transport Calculations without Spatial Homogenisation, 2001, NEA/NSC, 2001.
  17. Y.A. Chao, Y.A. Shatilla, Conformal mapping and hexagonal nodal methods - II: implementation in the ANC-H code, Nucl. Sci. Eng. 121 (2) (1995) 210-225, https://doi.org/10.13182/NSE95-A28559.
  18. D. Lu, C. Guo, Development and validation of a three-dimensional diffusion code based on a high order nodal expansion method for hexagonal-z geometry, Science and Technology of Nuclear Installations 2016 (2016), https://doi.org/10.1155/2016/6340652.
  19. C. Chang, Research on the Fast Reactor Core Physics Uncertainty Analysis Method Based on Statistical Sampling Method, North China Electric Power University, 2022 (in Chinese).
  20. K. Mikityuk, A. Vasiliev, P. Fomichenko, T. Schepetina, S. Subbotin, P. Alekseev, RBEC-M lead-bismuth cooled fast reactor: optimization of conceptual decisions, International Conference on Nuclear Engineering, Proceedings, ICONE 2 (2002) 701-709, https://doi.org/10.1115/ICONE10-22329.
  21. H. Zifeng, Research on Reconstruction and Linearization of Resonance Cross Section and Fabrication Method of Ultrafine Energy Group Cross Section of Fast Reactor, North China Electric Power University, 2021 (in Chinese).