Method to improve measurement accuracy for bypass temperature of reactor coolant system in nuclear power plants

被引:0
|
作者
Chen, Jing [1 ]
Chen, Ke [1 ]
Huo, Yujia [1 ]
Li, Hongxia [1 ]
Yu, Junhui [1 ]
Li, Xiaofen [1 ]
机构
[1] Science and Technology on Reactor System Design Technology, Nuclear Power Institute of China, Chengdu,610041, China
来源
关键词
D O I
10.13832/j.jnpe.2015.02.0093
中图分类号
学科分类号
摘要
引用
收藏
页码:93 / 95
相关论文
共 50 条
  • [31] INSTRUMENTATION DEVICE AND SURFACE CONTROL TECHNOLOGY FOR COOLANT PIPING SYSTEM OF NUCLEAR POWER PLANTS
    Nishimura, Akihiko
    Terada, Takaya
    Shimada, Yukihiro
    Yonemoto, Yukihiro
    Yamada, Tomonori
    PROCEEDINGS OF THE 20TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING AND THE ASME 2012 POWER CONFERENCE - 2012, VOL 1, 2012, : 107 - 111
  • [32] KEY TECHNOLOGIES RESEARCH FOR THE IMPLEMENTATION OF IN-SERVICE INSPECTION STRATEGIES OPTIMIZING FOR THE REACTOR COOLANT SYSTEM OF IN-SERVICE NUCLEAR POWER PLANTS
    Shen Yunhai
    Deng Feng
    Duan Yongqiang
    Yu Xiaoquan
    Ye Shuixiang
    PROCEEDINGS OF 2024 31ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 1, ICONE31 2024, 2024,
  • [33] Noise Reduction Method to Improve Temperature Measurement Accuracy of Distributed Temperature Sensor
    Miao, Sun
    Tang Yuquan
    Yang Shuang
    Zhao Xiaohu
    Zhang Zhirong
    Zhuang Feiyu
    LASER & OPTOELECTRONICS PROGRESS, 2022, 59 (19)
  • [34] REACTOR REDO Advanced fuels could improve the safety and economics of nuclear power plants
    McCullum, Rod
    SCIENTIFIC AMERICAN, 2019, 320 (05) : 72 - 75
  • [35] Integral nuclear power reactor with natural coolant circulation. Investigation of passive RHR system
    Samoilov, OB
    Kuul, VS
    Malamud, VA
    Tarasov, GI
    NUCLEAR ENGINEERING AND DESIGN, 1996, 165 (1-2) : 259 - 264
  • [36] ERROR OF MEASUREMENT OF COOLANT TEMPERATURE IN VVER-440 REACTOR
    SLESAREVSKII, SO
    BELAVSKII, AM
    KOROTENKO, MN
    LYUBARSKII, VS
    PAVLENKO, VP
    SNIGEREV, VA
    TKACHENKO, AV
    SOVIET ATOMIC ENERGY, 1989, 67 (05): : 853 - 855
  • [37] POSSIBILITY OF FRACTURES IN LARGE COMPONENTS OF PRIMARY COOLANT LOOP OF PRESSURIZED WATER REACTOR NUCLEAR-POWER PLANTS
    BERGEMANN, W
    KERNENERGIE, 1973, 16 (06): : 183 - 193
  • [38] A practical method to improve phasor and power measurement accuracy of DFT algorithm
    Wang, MH
    Sun, YZ
    IEEE TRANSACTIONS ON POWER DELIVERY, 2006, 21 (03) : 1054 - 1062
  • [39] THE CONTINUOUS MEASUREMENT OF COOLANT LIQUID-LEVEL IN A NUCLEAR-REACTOR
    MARSHALL, RK
    MOHR, CL
    MCDUFFIE, PN
    SCOGGIN, RA
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1982, 43 : 564 - 567
  • [40] Determination of Loss of Coolant Accident (LOCA) in Nuclear Power Plants Using Signal Processing Method
    Mahmoodi, R.
    Shahriari, M.
    Zolfaghari, A.
    ENGINEERING LETTERS, 2009, 17 (04)