FreeCAD based Monte Carlo modeling approach for fusion reactor facilities | |
Li, Jin-Yang1,2; Gu, Long1,2,5; Xu, Hu-Shan1,2; Dai, Yong1,3; Zhang, You-Peng4; Yu, Rui1,2; Zhang, Lu1,2; Wang, Da-Wei1,5; Jiang, Wei1 | |
刊名 | FUSION ENGINEERING AND DESIGN |
2020-06-01 | |
卷号 | 155页码:10 |
关键词 | FreeCAD Monte Carlo method MCNPX fast ray-casting method B-rep CSG |
ISSN号 | 0920-3796 |
DOI | 10.1016/j.fusengdes.2020.111711 |
英文摘要 | MCNPX is a general purpose multi-particle Monte Carlo transport code with board ranges of energies, which has already been widely employed in the fields of radiotherapy, nuclear engineering, and nuclear fusion research. The neutronics design and analysis of fusion reactor facilities using MCNPX have been considered as the time consuming and error prone tasks. For example, the ITER-type models include a lot of nested structures and complicated high-order curve surfaces, which can not be easily described in the mathematics expressions, and the spline surfaces are also not supported by the native syntax of MCNPX. In this context, a code system called CAD-PSMC (FreeCAD based parsing script for MCNPX) has been developed in IMPCAS (Institute of Modern Physics, Chinese academy of Sciences) for the study of modeling conversion problem in ITER-type neutron calculations. Two kinds of methods have been provided and discussed in the framework of this code, including the establishing of the mapping relationship between the specification tree and the build-in boolean operations in consideration of the complicated hierarchical structures, and the demonstration of fast ray-casting technology based iteration method coupling with the mesh-oriented optimized CAD geometries in solving the high-order curve surfaces related problems. Finally, the stability and feasibility of the CAD-PSMC have been verified and validated through the comparison with the selected reference models and the neutronic simulation results of the ITER-type benchmark model. |
资助项目 | Light of West China type B[E0233501] ; The main equipment, key materials, technology research, development and application of the fourth generation lead based fast reactor[Y9391601] |
WOS关键词 | DESIGN ; ACCELERATION ; BENCHMARKING ; GEOMETRY ; SYSTEM ; MCNPX |
WOS研究方向 | Nuclear Science & Technology |
语种 | 英语 |
出版者 | ELSEVIER SCIENCE SA |
WOS记录号 | WOS:000535910900003 |
资助机构 | Light of West China type B ; The main equipment, key materials, technology research, development and application of the fourth generation lead based fast reactor |
内容类型 | 期刊论文 |
源URL | [http://119.78.100.186/handle/113462/140857] |
专题 | 中国科学院近代物理研究所 |
通讯作者 | Gu, Long |
作者单位 | 1.Chinese Acad Sci, Inst Modern Phys, Lanzhou 730000, Peoples R China 2.Univ Chinese Acad Sci, Sch Nucl Sci & Technol, Beijing 100049, Peoples R China 3.Paul Scherrer Inst, CH-5232 Villigen, Switzerland 4.Fudan Univ, Inst Modern Phys, Shanghai 200433, Peoples R China 5.Lanzhou Univ, Sch Nucl Sci & Technol, Lanzhou 730000, Peoples R China |
推荐引用方式 GB/T 7714 | Li, Jin-Yang,Gu, Long,Xu, Hu-Shan,et al. FreeCAD based Monte Carlo modeling approach for fusion reactor facilities[J]. FUSION ENGINEERING AND DESIGN,2020,155:10. |
APA | Li, Jin-Yang.,Gu, Long.,Xu, Hu-Shan.,Dai, Yong.,Zhang, You-Peng.,...&Jiang, Wei.(2020).FreeCAD based Monte Carlo modeling approach for fusion reactor facilities.FUSION ENGINEERING AND DESIGN,155,10. |
MLA | Li, Jin-Yang,et al."FreeCAD based Monte Carlo modeling approach for fusion reactor facilities".FUSION ENGINEERING AND DESIGN 155(2020):10. |
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