Dongchuan Ying

China General Nuclear Power Corporation (China)

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Tongqiang Dang

Hefei Institutes of Physical Science

Qin Zeng

Sichuan Normal University

Guozhong Wang

University of Science and Technology of China

Qi Yang

Chinese Academy of Sciences

Pengcheng Long

O/E Land (Canada)

Songqian Tang

China General Nuclear Power Corporation (China)

M. Loughlin

Culham Centre for Fusion Energy

Huanwen Lyu

China General Nuclear Power Corporation (China)

Xiao Feng

Xi'an Jiaotong University

Teruya Tanaka

National Institute for Fusion Science

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Chinese Academy of Sciences

University of Science and Technology of China

Hefei Institutes of Physical Science

Institute of Plasma Physics

China General Nuclear Power Corporation (China)

Hefei University of Technology

Peking University

University of Chinese Academy of Sciences

Sichuan University

National Institute for Fusion Science

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遺伝的アルゴリズムに基づく核融合法の研究【JST・京大機械翻訳】

Hedongli Gongcheng (2016)

Dongchuan Ying Xiao Feng Hongyue Zhang Lyu Huanwen Tan Yi

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Research and Implementation of a geometry coupled visual analysis system for MCNP

Chinese Journal of Nuclear Science and Engineering (2010)

Fan Yanchang Long Pengcheng Qin Zeng Junjun Zhang Dongchuan Ying

The post-processing capability of the current MCNP is not enough to effectively and sufficiently analyze calculation results of complex problems.In the paper,a geometry coupled visual analysis system for MCNP was self-developed in FDS Team by using scientific visualization technology,GPU(graphics processing unit)visual programming technology,and the reversion engine of MCAM.The visual analysis system was implemented to support data extraction and manipulation based on graphics user interface,three-dimensional plotting of tally results,and visual analysis of the results with geometries.And the system has been tested by many de facto cases,such as ITER.Testing results showed that the system provided an intuitively and effectively visual analysis approach for the post-processing of MCNP and obviously enhanced the analysis efficiency.

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Progress and Applications of MCAM: Monte Carlo Automatic Modeling Program for Particle Transport Simulation

Progress in Nuclear Science and Technology (2011)

Guozhong Wang Jian Xiong Pengcheng Long Dianxi Wang Kai Zhao

MCAM (Monte Carlo Automatic Modeling program for particle transport simulation) was developed by FDS Team as a bi-directional interface program between general CAD systems and Monte Carlo particle transport simulation codes.The physics and material modeling and void space modeling functions were improved and the free-form surfaces processing function was developed recently.The applications to the ITER (International Thermonuclear Experimental Reactor) building model and FFHR (Force Free Helical Reactor) model have demonstrated the feasibility, effectiveness and maturity of MCAM latest version for nuclear applications with complex geometry.

Neutron Transport

Thermonuclear Fusion

10.15669/pnst.2.821

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A Monte Carlo Code Developed for Radiation Shielding Calculations Based on RMC

Springer proceedings in physics (2023)

Dongchuan Ying Huanwen Lyu Songqian Tang Xiaotong Shang Xiao Feng

Variance reduction

Code (set theory)

10.1007/978-981-19-8899-8_110

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Development of a Geometry-Coupled Visual Analysis System for MCNP

Progress in Nuclear Science and Technology (2011)

Pengcheng Long Qin Zeng Tao He Junjun Zhang Dongchuan Ying

MCNP is a general and powerful Monte Carlo code for photons, neutrons, and electrons transport simulation and is widely used in nuclear analysis.However, external specialized data analysis codes may be needed to analyze complex MCNP calculation results.Especially, there is a lack of efficient data analysis codes which supports geometry-coupled visual analysis.To address the post-processing concerns, a geometry-coupled visual analysis system for MCNP, was developed with 3D scientific visualization and graphics processing unit programming technologies by FDS Team.It was designed and implemented to provide friendly graphical user interface based data manipulation, 3D plotting of tally results, and visual data analysis coupled with geometries.Testing and preliminary application results showed that the system provided a satisfied visual analysis approach for the post-processing of MCNP and obviously enhanced the analysis efficiency.

10.15669/pnst.2.280

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Citations (8)

Activation of FLiBe coolant in the molten salt reactor

Annals of Nuclear Energy (2019)

Dongchuan Ying Hongrun Yang Huanwen Lyu Ying Tan Futing Jing

Molten salt reactor

Nuclide

Neutron activation

10.1016/j.anucene.2019.01.038

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Citations (7)