Study on Monte Carlo Importance Sampling Method Based on Unstructured Mesh

Shu Hanlin; Cao Liangzhi; He Qingming; Dai Tao; Huang Zhanpeng

doi:10.13832/j.jnpe.2023.03.0028

Volume 44 Issue 3

Jun. 2023

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Shu Hanlin, Cao Liangzhi, He Qingming, Dai Tao, Huang Zhanpeng. Study on Monte Carlo Importance Sampling Method Based on Unstructured Mesh[J]. Nuclear Power Engineering, 2023, 44(3): 28-37. doi: 10.13832/j.jnpe.2023.03.0028

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Shu Hanlin, Cao Liangzhi, He Qingming, Dai Tao, Huang Zhanpeng. Study on Monte Carlo Importance Sampling Method Based on Unstructured Mesh[J]. Nuclear Power Engineering, 2023, 44(3): 28-37. doi: 10.13832/j.jnpe.2023.03.0028

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Study on Monte Carlo Importance Sampling Method Based on Unstructured Mesh

doi: 10.13832/j.jnpe.2023.03.0028

School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, 710049, China

Received Date: 2022-07-26
Rev Recd Date: 2022-09-03
Publish Date: 2023-06-15

Abstract

Abstract

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 (S_N) 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 S_N 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.
- Neutron transport code,
- Monte Carlo method,
- Consistent adjoint driven importance sampling (CADIS) method,
- Unstructured mesh

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References(15)

References

[1]	曹良志, 谢仲生, 李云召. 近代核反应堆物理分析[M]. 北京: 中国原子能出版社, 2017: 310-313.
[2]	MUNK M, SLAYBAUGH R N. Review of hybrid methods for deep-penetration neutron transport[J]. Nuclear Science and Engineering, 2019, 193(10): 1055-1089. doi: 10.1080/00295639.2019.1586273
[3]	WAGNER J C, HAGHIGHAT A. Automated variance reduction of Monte Carlo shielding calculations using the discrete ordinates adjoint function[J]. Nuclear Science and Engineering, 1998, 128(2): 186-208. doi: 10.13182/NSE98-2
[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[R]. Oak Ridge: Oak Ridge National Laboratory, 2015.
[5]	PEPLOW D E. Monte Carlo shielding analysis capabilities with MAVRIC[J]. Nuclear Technology, 2011, 174(2): 289-313. doi: 10.13182/NT174-289
[6]	ALWIN J L, SPENCER J B, FAILLA G A. Criticality accident alarm system analysis using MCNP6.2 constructive solid geometry/unstructured mesh hybrid[Z]. 2019.
[7]	WAREING T A, MCGHEE J M, MOREL J E. ATTILA: a three-dimensional, unstructured tetrahedral mesh discrete ordinates transport code[J]. Transactions of the American Nuclear Society, 1996, 75: 146-147.
[8]	DOMINESEY K A, KOWAL P J, EUGENIO J A, et al. Scientific workflows for MCNP6 and proteus within the neams workbench[C]//International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future. Cambridge: EDP Sciences, 2021: 06052.
[9]	WARNER P, DE OLIVEIRA C R E. Validation of the 3D finite element transport theory code EVENT for shielding applications[J]. Journal of Nuclear Science and Technology, 2000, 37(S1): 466-470.
[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[J]. Annals of Nuclear Energy, 2022, 169: 108943. doi: 10.1016/j.anucene.2021.108943
[11]	REED W H, HILL T R. Triangular mesh methods for the neutron transport equation: Technical Report LA-UR-73-479[R]. Mex: Los Alamos Scientific Laboratory, 1973.
[12]	HE Q M, ZHENG Q, LI J, et al. NECP-MCX: A hybrid Monte-Carlo-Deterministic particle-transport code for the simulation of deep-penetration problems[J]. Annals of Nuclear Energy, 2021, 151: 107978. doi: 10.1016/j.anucene.2020.107978
[13]	REMEC I, KAM F B K. H. B. Robinson-2 pressure vessel benchmark: NUREG/CR-6453; ORNL/TM-13204[R]. Washington: US Nuclear Regulatory Commission, 1998.
[14]	XU L F, CAO L Z, ZHENG Y Q, et al. Development of a new parallel S_N code for neutron-photon transport calculation in 3-D cylindrical geometry[J]. Progress in Nuclear Energy, 2017, 94: 1-21. doi: 10.1016/j.pnucene.2016.09.005
[15]	EL-MEHALAWI M, MILLER R A. A database system of mechanical components based on geometric and topological similarity. Part I: representation[J]. Computer-Aided Design, 2003, 35(1): 83-94. doi: 10.1016/S0010-4485(01)00177-4