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Volume 44 Issue 4
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Wang Xinyu, Zhang Bin, Chen Yixue. Research on Simulation of Neutron Transport with Thick Diffusion Limit in Curved Meshes[J]. Nuclear Power Engineering, 2023, 44(4): 41-48. doi: 10.13832/j.jnpe.2023.04.0041
Citation: Wang Xinyu, Zhang Bin, Chen Yixue. Research on Simulation of Neutron Transport with Thick Diffusion Limit in Curved Meshes[J]. Nuclear Power Engineering, 2023, 44(4): 41-48. doi: 10.13832/j.jnpe.2023.04.0041

Research on Simulation of Neutron Transport with Thick Diffusion Limit in Curved Meshes

doi: 10.13832/j.jnpe.2023.04.0041
  • Received Date: 2022-10-08
  • Rev Recd Date: 2022-11-26
  • Publish Date: 2023-08-15
  • Discrete ordinate method is one of the main numerical methods for solving the problem of neutron transport with thick diffusion limit. Its commonly used spatial discrete schemes, such as finite difference scheme, are easy to cause numerical diffusion in optical thick media, and the application of discrete ordinate method has certain limitations due to the lack of coarse mesh accuracy and difficulty in adapting to complex geometry. In this paper, Galerkin method is used to derive discrete ordinate equations in weak form or variational form. Based on the idea of discontinuous finite element, the Lagrangian finite element basis function in the higher-order curved meshes is constructed to establish the higher-order finite element discrete scheme of the transport equation. Two manufactured solution examples, the IAEA EIR-2 benchmark problem and the thick diffusion limit example, are selected for modeling and transport calculation, and the calculation accuracy and convergence of the spatial discrete scheme are tested and verified, and its thick diffusion limit characteristics are analyzed. The numerical results show that the relative error between the calculated results of high-order discontinuous finite element scheme and the reference value is less than 1%, and it also has high calculation accuracy and convergence rate in curved meshes. The discrete scheme can effectively solve the problem of neutron transport with thick diffusion limit in curved meshes. It has good numerical characteristics, and has the asymptotic preservation property of diffusion limit under optical thick diffusion limit.

     

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  • [1]
    GRAZIANI F. Computational methods in transport[M]. New York: Springer, 2004: 527-530.
    [2]
    ATZENI S, MEYER-TER-VEHN J. 惯性聚变物理[M]. 沈百飞, 译. 北京: 科学出版社, 2008: 162-196.
    [3]
    LEWIS E E, MILLER W F JR. Computational methods of neutron transport[M]. La Grange Park: American Nuclear Society, 1993: 116-153.
    [4]
    LATHROP K D. Spatial differencing of the transport equation: positivity vs. accuracy[J]. Journal of Computational Physics, 1969, 4(4): 475-498. doi: 10.1016/0021-9991(69)90015-1
    [5]
    PETROVIC B, HAGHIGHAT A. New directional theta-weighted SN differencing scheme and its application to pressure vessel fluence calculations[C]//Proceedings of Radiation Protection and Shielding Topical Meeting. Falmouth, 1996: 3-10.
    [6]
    LARSEN E W, ALCOUFFE R E. Linear characteristic method for spatially discretizing the discrete ordinates equations in (X, Y)-geometry: LA-UR-81-101[R]. Los Alamos: Los Alamos Scientific Laboratory, 1981.
    [7]
    AZMY Y Y. Arbitrarily high order characteristic methods for solving the neutron transport equation[J]. Annals of National Energy, 1992, 19(10-12): 593-606. doi: 10.1016/0306-4549(92)90004-U
    [8]
    REED W H, HILL T R. Triangular mesh methods for the neutron transport equation: LA-UR-73-479[R]. Los Alamos: Los Alamos Scientific Laboratory, 1973.
    [9]
    MOREL J E, DENDY J E JR, WAREING T A. Diffusion-accelerated solution of the two-dimensional Sn equations with bilinear-discontinuous differencing[J]. Nuclear Science and Engineering, 1993, 115(4): 304-319. doi: 10.13182/NSE93-A24061
    [10]
    MOREL J E, WAREING T A, SMITH K. A linear-discontinuous spatial differencing scheme for Sn radiative transfer calculations[J]. Journal of Computational Physics, 1996, 128(2): 445-462. doi: 10.1006/jcph.1996.0223
    [11]
    WANG Y Q, RAGUSA J C. A high-order discontinuous Galerkin method for the SN transport equations on 2D unstructured triangular meshes[J]. Annals of Nuclear Energy, 2009, 36(7): 931-939. doi: 10.1016/j.anucene.2009.03.002
    [12]
    WANG Y Q, RAGUSA J C. On the convergence of DGFEM applied to the discrete ordinates transport equation for structured and unstructured triangular meshes[J]. Nuclear Science and Engineering, 2009, 163(1): 56-72. doi: 10.13182/NSE08-72
    [13]
    WANG Y Q, RAGUSA J C. Standard and goal-oriented adaptive mesh refinement applied to radiation transport on 2D unstructured triangular meshes[J]. Journal of Computational Physics, 2011, 230(3): 763-788. doi: 10.1016/j.jcp.2010.10.018
    [14]
    HACKEMACK M W, RAGUSA J C. Quadratic serendipity discontinuous finite element discretization for SN transport on arbitrary polygonal grids[J]. Journal of Computational Physics, 2018, 374: 188-212. doi: 10.1016/j.jcp.2018.05.032
    [15]
    洪振英,袁光伟,魏军侠. 球几何中子输运保正线性间断有限元格式[J]. 强激光与粒子束,2017, 29(7): 076001. doi: 10.11884/HPLPB201729.160320
    [16]
    LARSEN E W, MOREL J E, MILLER W F. Asymptotic solutions of numerical transport problems in optically thick, diffusive regimes[J]. Journal of Computational Physics, 1987, 69(2): 283-324. doi: 10.1016/0021-9991(87)90170-7
    [17]
    CHEN Y X, ZHANG B, ZHANG L, et al. ARES: a parallel discrete ordinates transport code for radiation shielding applications and reactor physics analysis[J]. Science and Technology of Nuclear Installations, 2017, 2017: 2596727.
    [18]
    ANDERSON R, ANDREJ J, BARKER A, et al. MFEM: a modular finite element methods library[J]. Computers & Mathematics with Applications, 2021, 81: 42-74.
    [19]
    SCHUNERT S, AZMY Y. Comparison of spatial discretization methods for solving the SN equations using a three-dimensional method of manufactured solutions benchmark suite with escalating order of nonsmoothness[J]. Nuclear Science and Engineering, 2015, 180(1): 1-29. doi: 10.13182/NSE14-77
    [20]
    KAVENOKY, STEPANEK J, SCHMIDT F. Transport theory and advanced reactor calculations: IAEA-TECDOC-254[R]. Vienna: International Atomic Energy Agency, 1981.
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