Nuclear Science and Techniques ›› 2019, Vol. 42 ›› Issue (2): 20502-020502.doi: 10.11889/j.0253-3219.2019.hjs.42.020502

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Visual analysis of source particle and its application in Monte Carlo transport simulation

Pei CAO1,2,Pengcheng LONG1,Quan GAN1(),Bin WU1,Lijuan HAO1   

  1. 1. Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei 230031, China
    2. University of Science and Technology of China, Hefei 230027, China
  • Received:2018-11-14 Revised:2018-12-10 Online:2019-02-10 Published:2019-02-19
  • Contact: Quan GAN E-mail:quan.gan@fds.org.cn
  • About author:CAO Pei, female, born in 1994, graduated from Shandong University in 2016, master student, focusing on modeling and visualization|CAO Pei, female, born in 1994, graduated from Shandong University in 2016, master student, focusing on modeling and visualization|GAN Quan, E-mail:<email>quan.gan@fds.org.cn</email>
  • Supported by:
    国家自然科学基金(No.11605233, No.71671179)、中国科学院信息化专项(No.XXH13506-104)、国家磁约束核聚变能发展研究专项项目(No.2015GB116000)、中国科学院合肥物质研究院院长基金(No.YZJJ201618)、国家科技部国家科技基础条件平台项目“国家基础科学数据共享服务平台”(No.DKA2017-12-02-17)、中国科学院合肥物质科学研究院项目(No.KP-2017-19)、安徽省重大科技专项项目(No.18030801135)、中国科学院青年创新促进会专项项目、产业化基金资助;Supported by National Natural Science Foundation of China (No.11605233, No.71671179), Information Project of Chinese Academy of Sciences (No.XXH13506-104), National Magnetic Confinement Fusion Program of China (No.2015GB116000), the President of Chinese Academy of Sciences Foundation for Young Project (No.YZJJ201618), National Fundamental Science Data Sharing Program (No.DKA2017-12-02-17), Project of Hefei Institutes of Physical Science, Chinese Academy of Sciences (No.KP-2017-19), Major Science and Technology Projects of Anhui Province(No.18030801135), Special Project of Youth Innovation Promotion Association of Chinese Academy of Sciences, Industrialization Fund

Abstract: Background

The high-fidelity particle transport numerical simulation for nuclear facility requires accurate and efficient source particles distribution.

Purpose

This study focuses on reviewing and analyzing the distribution feature of source particles intuitively in nuclear facility and presents a visual analysis method for source particles.

Methods

Based on self-adaptive segmented tree and pre-build geometry library, the features of geometry and rendering attributes were extracted to dynamically create the segmented trees. Then, over million source particles were shown in the form of two-dimensional and three-dimensional visualization. Finally, this method was verified on neutron source modeling and neutron collimation device design for shielding analysis of VENUS-3 reactor.

Results

The results show that the proposed method is helpful for users to complete high fidelity modeling and the design and optimization of nuclear facilities.

Conclusion

To a certain extent, it can improve the efficiency and correctness of modeling during the procedure of calculation.

Key words: Nuclear devices, Transport simulation, Source particles visualization, Self-adaptive segmented tree

CLC Number: 

  • TL329+.2