Research on Automatic Modeling Method of TORT Program Based on CAD Model

Xu Fangyuan; Yang Chao; Yu Tao; Chen Zhenping; Huang Guocai; Li Leiming; Li Yukun; Xian Xirui; Du Hua

doi:10.13832/j.jnpe.2023.04.0049

Volume 44 Issue 4

Aug. 2023

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Article Navigation > Nuclear Power Engineering > 2023 > 44(4): 49-54

Xu Fangyuan, Yang Chao, Yu Tao, Chen Zhenping, Huang Guocai, Li Leiming, Li Yukun, Xian Xirui, Du Hua. Research on Automatic Modeling Method of TORT Program Based on CAD Model[J]. Nuclear Power Engineering, 2023, 44(4): 49-54. doi: 10.13832/j.jnpe.2023.04.0049

Citation:

Xu Fangyuan, Yang Chao, Yu Tao, Chen Zhenping, Huang Guocai, Li Leiming, Li Yukun, Xian Xirui, Du Hua. Research on Automatic Modeling Method of TORT Program Based on CAD Model[J]. Nuclear Power Engineering, 2023, 44(4): 49-54. doi: 10.13832/j.jnpe.2023.04.0049

Citation:

Xu Fangyuan, Yang Chao, Yu Tao, Chen Zhenping, Huang Guocai, Li Leiming, Li Yukun, Xian Xirui, Du Hua. Research on Automatic Modeling Method of TORT Program Based on CAD Model[J]. Nuclear Power Engineering, 2023, 44(4): 49-54. doi: 10.13832/j.jnpe.2023.04.0049

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Research on Automatic Modeling Method of TORT Program Based on CAD Model

doi: 10.13832/j.jnpe.2023.04.0049

Xu Fangyuan^{1, 2
,},
Yang Chao^{1, 2},
Yu Tao^{1, 2
,
,},
Chen Zhenping^{1, 2},
Huang Guocai^{1, 2},
Li Leiming^{1, 2},
Li Yukun^{1, 2},
Xian Xirui³,
Du Hua³

1.
School of Nuclear Science and Technology, University of South China, Hengyang, Hunan, 421001, China
2.
Hunan Engineering & Technology Research Center for Virtual Nuclear Reactor, Hengyang, Hunan, 421001, China
3.
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2022-09-02
Rev Recd Date: 2023-02-27
Publish Date: 2023-08-15

Abstract

Abstract

Aiming at the problems of complex geometry of reactor shielding structure, limited geometric processing ability, low efficiency and error prone of traditional manual modeling, based on the multi-objective modeling and simulation platform for radiation transport (MOSRT), the volume weight homogenization method of discrete mesh materials is used to homogenize the discrete meshes of multi-materials, and the fine transformation from CAD model to three-dimensional discrete ordinate method (S_N) calculation program TORT shielding calculation model is realized. Based on the Kobayashi and NUREG-CR-6115 benchmark models, the automatic modeling method is verified. The results show that for the Kobayashi benchmark problem, the automatic modeling method is completely consistent with the manual modeling results. For the NUREG-CR-6115 benchmark problem, the maximum error between the automatic modeling method and the reference solution is 12.2%. The verification results show the effectiveness and correctness of the automatic modeling method.
- Automatic modeling,
- Discrete ordinate method (S_N),
- Homogenization of discrete mesh materials,
- CAD model

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References(10)

References

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