Key Technology and Prospects of Digital Twin in Field of Advanced Nuclear Energy

被引：0
|
作者：
Hu M. [1 ]
Kong F. [2 ,3 ]
Yu D. [2 ]
Yang J. [1 ]
机构：
[1] School of Energy and Power Engineering, Huazhong University of Science and Technology, Wuhan
[2] Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei
[3] Science Island Branch of Graduate School, University of Science and Technology of China, Hefei
来源：
Dianwang Jishu/Power System Technology | 2021年 / 45卷 / 07期
关键词：
Digital reactor; Digital twin; Error diagnosis; GEMINA project;
D O I：
10.13335/j.1000-3673.pst.2021.0335
中图分类号：
学科分类号：
摘要：
Digital twin is a technology to realize the mapping of a physical system to a digital model of the information space. It is listed as one of the six cutting edge technologies in the future national defense and aerospace industry. It is also expected to play an important role in the advanced nuclear energy systems such as the intelligent control of a nuclear power plant, the space reactor, the small module reactor, etc. In recent years, some countries have launched projects to develop digital twin technology for the nuclear reactors, with the goal of reducing their operation and maintenance costs of the nuclear power plants significantly. The research and development of digital twin systems for space nuclear power and lunar-based nuclear power devices has also received attention. This article comprehensively describes the research status and development directions of the digital twin technology in the field of the advanced nuclear energy. It proposes a multi-dimensional evaluation digital model suitable for nuclear reactors, initially builds an error diagnosis process, and discusses the key technology and the potential application of digital twin in the field of the advanced nuclear energy. © 2021, Power System Technology Press. All right reserved.
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页码：2514 / 2522
页数：8
相关论文
共 76 条
  • [51] YANG Ye, DENG Chengcheng, YANG Jun, Best estimate plus uncertainty analysis of a small-break LOCA on an advanced generation-III pressurized water reactor, International Journal of Energy Research, (2020)
  • [52] POURGOL-MOHAMAD M, MOSLEH A, MODARRES M., Structured treatment of model uncertainty in complex thermal-hydraulics codes: technical challenges, prospective and characterization, Nuclear Engineering and Design, 241, 1, pp. 285-295, (2011)
  • [53] D'AURIA F, GALASSI G M., Scaling in nuclear reactor system thermal-hydraulics, Nuclear Engineering and Design, 240, 10, pp. 3267-3293, (2010)
  • [54] BUCALOSSI A, PETRUZZI A, KRISTOF M, Et al., Comparison between best-estimate-plus-uncertainty methods and conservative tools for nuclear power plant licensing, Nuclear Technology, 172, 1, pp. 29-47, (2010)
  • [55] REED J, TUNLEY C., The application of advanced visualisation and simulation techniques in control room design and operator training[nuclear power plants, Proceedings of the 1997 IEEE Sixth Conference on Human Factors and Power Plants, pp. 13-18, (1997)
  • [56] DIXON J, MARKIDIS S, LUO Cheng, Et al., Three-dimensional, virtual, game-like environments for education and training, Transactions, 97, 1, pp. 915-917, (2007)
  • [57] TAO Fei, SUI Fangyuan, LIU Ang, Et al., Digital twin-driven product design framework, International Journal of Production Research, 57, 12, pp. 3935-3953, (2019)
  • [58] LIU Zhansheng, BAI Wenyan, DU Xiuli, Et al., Digital twin-based safety evaluation of prestressed steel structure, Advances in Civil Engineering, pp. 1-10, (2020)
  • [59] Energy", Part 50, "Domestic Licensing of Production and Utilization Facilities", Sec.50.46, "Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors, (1996)
  • [60] BOYACK B E, CATTON I, DUFFEY R B, Et al., Quantifying reactor safety margins part 1: an overview of the code scaling, applicability, and uncertainty evaluation methodology, Nuclear Engineering and Design, 119, 1, pp. 1-15, (1990)
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