Diversity analysis of htr reactor trip protection system

被引：0
|
作者：
Xu Z. [1 ]
Xue F. [1 ]
Gao Q.-Y. [1 ]
Na F.-L. [1 ]
机构：
[1] Nuclear Safety Technology Center, Suzhou Nuclear Power Research Institute Co., Ltd, Suzhou
来源：
| 1600年 / Atomic Energy Press卷 / 51期
关键词：
Common cause failure; Diversity; Diversity actuation system; HTR; NUREG/CR-7007; Reactor trip protection;
D O I：
10.7538/yzk.2017.51.12.2344
中图分类号：
TL4 [各种核反应堆、核电厂];
学科分类号：
082703 ;
摘要：
To evaluate the diversity features of the HTR reactor trip protection system, the assessment method defined in NUREG/CR-6303 was used and the quantitative diversity evaluation method defined in NUREG/CR-7007 was selected for calculating the standardized diversity value, upon the analysis and identification of the 25 diversity attributes among 7 categories. On account of the weakness that the diversity value of the system failed to meet the acceptance threshold of NRC and from point view of the reality of the project, a feasible improvement was proposed. The recalculation result shows that the proposal can significantly improve the quantitative diversity value of the system. © 2017, Editorial Board of Atomic Energy Science and Technology. All right reserved.
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收藏
页码：2344 / 2351
页数：7
相关论文
共 14 条
  • [1] Li Z., Chen L., Xu X., Et al., Inherent safety features of the modular HTGT, Nuclear Safety, 12, 3, pp. 1-4, (2013)
  • [2] Wu Z., Xiao H., Safety features of the modular HTGR, High Technology Letters, 11, pp. 34-38, (1994)
  • [3] Li D., Xiong H., Guo C., Et al., Development of HTR-PM reactor protection system engineering prototype, Instrumentation Customer, 20, 5, pp. 36-38, (2013)
  • [4] Lu D., Zhang B., Zuo X., Et al., High temperature gas cooled reactor nuclear power plant protection system periodic test project design, Automation Panorama, 10, pp. 60-62, (2016)
  • [5] Zhao Y., Li G., Bai T., An overview on the FirmSys based design of digital protection system with nuclear safety standard for the third generation of PWR nuclear power station, Automation Panorama, 9, pp. 56-60, (2012)
  • [6] Us N., NUREG/CR-6303 Method for performing diversity and defense-in-depth analyses of reactor protection systems, (1994)
  • [7] Us N., NUREG/CR-7007 Diversity strategies for nuclear power plant instrumentation and control systems, (2009)
  • [8] Guo C., Li D., Xiong H., Development and analysis of fault tree model of HTR-PM reactor protection system, Atomic Energy Science and Technology, 47, 11, pp. 2063-2070, (2013)
  • [9] Xu Z., Jiang D.Q., A new ALS based PMS design and its evaluations, World Journal of Nuclear Science & Technology, 6, 1, pp. 1-14, (2016)
  • [10] Xu Z., Ding D., Zhang Y., Optimized design of DAS based on NUREG/CR-7007, Atomic Energy Science and Technology, 50, 1, pp. 156-163, (2016)
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