Study on Monte Carlo Importance Sampling Method Based on Unstructured Mesh

被引:0
|
作者
Shu H. [1 ]
Cao L. [1 ]
He Q. [1 ]
Dai T. [1 ]
Huang Z. [1 ]
机构
[1] School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an
来源
关键词
Consistent adjoint driven importance sampling (CADIS) method; Monte Carlo method; Neutron transport code; Unstructured mesh;
D O I
10.13832/j.jnpe.2023.03.0028
中图分类号
学科分类号
摘要
In order to improve the modeling and calculation accuracy of the traditional Consistent Adjoint Driven Importance Sampling (CADIS) method that relies on structural-mesh finite-difference discrete ordinate (SN) code to determine the importance distribution of particles to further enhance its capability of dealing with complex-geometric deep-penetration problems, a fully automatic unstructured-mesh CADIS method is studied and implemented in this paper, parallel three-dimensional unstructured-mesh neutron-photon-coupled transport code NECP-SUN based on SN method and discontinuous finite element method (DFEM) is developed and embedded into the Monte Carlo code NECP-MCX as adjoint transport solver. The numerical results of the calculations of the HBR-2 benchmark and the fast-neutron fluence rate of the toroidal field coil boxes in the Chinese Fusion Engineering Test Reactor (CFETR) show that the unstructured-mesh CADIS method has stronger adaptability to complex geometry than the traditional CADIS method, and the results obtained are relatively lower in relative statistical error and closer to the measurements; the figure of merit (FOM) is increased by 1~3 orders than that of direct Monte Carlo simulation. Therefore, the unstructured-mesh CADIS method studied in this paper can better handle deep-penetration problems with complex geometry. © 2023 Yuan Zi Neng Chuban She. All rights reserved.
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页码:28 / 37
页数:9
相关论文
共 16 条
  • [1] pp. 310-313, (2017)
  • [2] MUNK M, SLAYBAUGH R N., Review of hybrid methods for deep-penetration neutron transport, Nuclear Science and Engineering, 193, 10, pp. 1055-1089, (2019)
  • [3] WAGNER J C, HAGHIGHAT A., Automated variance reduction of Monte Carlo shielding calculations using the discrete ordinates adjoint function, Nuclear Science and Engineering, 128, 2, pp. 186-208, (1998)
  • [4] MOSHER S W, JOHNSON S R, BEVILL A M, Et al., ADVANTG —an automated variance reduction parameter generator: ORNL/TM-2013/416 Rev. 1, (2015)
  • [5] PEPLOW D E., Monte Carlo shielding analysis capabilities with MAVRIC, Nuclear Technology, 174, 2, pp. 289-313, (2011)
  • [6] ALWIN J L, SPENCER J B, FAILLA G A., Criticality accident alarm system analysis using MCNP6.2 constructive solid geometry/unstructured mesh hybrid, (2019)
  • [7] WAREING T A, MCGHEE J M, MOREL J E., ATTILA: a three-dimensional, unstructured tetrahedral mesh discrete ordinates transport code, Transactions of the American Nuclear Society, 75, pp. 146-147, (1996)
  • [8] DOMINESEY K A, KOWAL P J, EUGENIO J A, Et al., Scientific workflows for MCNP6 and proteus within the neams workbench, International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, (2021)
  • [9] WARNER P, DE OLIVEIRA C R E., Validation of the 3D finite element transport theory code EVENT for shielding applications, Journal of Nuclear Science and Technology, 37, pp. 466-470, (2000)
  • [10] MIAO J X, FANG C, WAN C H, Et al., Development and preliminary application of deterministic code NECP-FISH for neutronics analysis of fusion-reactor blanket, Annals of Nuclear Energy, 169, (2022)