Extended Development and Application of CAD-based Transport in RMC

Shen Pengfei; Wang Kan; Liu Zhaoyuan; Liang Jingang; Liu Shichang

doi:10.13832/j.jnpe.2024.S2.0055

Volume 45 Issue S2

Jan. 2025

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Article Navigation > Nuclear Power Engineering > 2024 > 45(S2): 55-62

Shen Pengfei, Wang Kan, Liu Zhaoyuan, Liang Jingang, Liu Shichang. Extended Development and Application of CAD-based Transport in RMC[J]. Nuclear Power Engineering, 2024, 45(S2): 55-62. doi: 10.13832/j.jnpe.2024.S2.0055

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Shen Pengfei, Wang Kan, Liu Zhaoyuan, Liang Jingang, Liu Shichang. Extended Development and Application of CAD-based Transport in RMC[J]. Nuclear Power Engineering, 2024, 45(S2): 55-62. doi: 10.13832/j.jnpe.2024.S2.0055

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Extended Development and Application of CAD-based Transport in RMC

doi: 10.13832/j.jnpe.2024.S2.0055

1.
Department of Engineering Physics, Tsinghua University, Beijing, 100084, China
2.
Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing, 100084, China
3.
School of Nuclear Science and Engineering, North China Electric Power University, Beijing, 100096, China

Received Date: 2024-07-24
Rev Recd Date: 2024-09-11
Publish Date: 2025-01-06

Abstract

Abstract

To enhance the capability of CAD-based transport in RMC, and provide a new calculation method for the CAD-based geometry transport modeling in Monte Carlo (MC) for new numerical reactors, in this study, firstly, an open-source meshing kernel is employed to process CAD models, realizing an autonomous CAD-based transport method throughout the entire process in the Monte Carlo code RMC. Subsequently, a hybrid geometric transport framework combining CAD and CSG geometry is developed, which improves the efficiency of geometric processing and Monte Carlo transport. The correctness of the autonomous CAD geometric processing method and the hybrid geometric transport method is verified through numerical calculations of fuel spheres, VERA-3A fuel assembly and other models. Compared with the existing CAD geometric modeling transportation methods, the hybrid geometric modeling transportation method has significantly improved the geometric processing time and the efficiency of Monte Carlo calculation. Therefore, the enhanced CAD-based transport method in RMC developed in this study can be used for neutron transport analysis calculations of new numerical reactors.
- Constructive solid geometry (CSG),
- Hybrid geometry,
- CAD geometry,
- RMC,
- Geometry meshing,
- Monte Carlo

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References(15)

References

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