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：
Hedongli Gongcheng/Nuclear Power Engineering | 2015年 / 36卷 / 02期
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
  • [1] MATERIALS FOR COMPONENTS OF THE REACTOR COOLANT SYSTEM OF NUCLEAR-POWER-PLANTS
    ERVE, M
    KERNTECHNIK, 1990, 55 (06) : 329 - 334
  • [2] Corrosion behaviour of reactor coolant system materials in nuclear power plants
    Kilian, R.
    Roth, A.
    Materials and Corrosion, 2002, 53 (10) : 727 - 739
  • [3] Corrosion behaviour of reactor coolant system materials in nuclear power plants
    Kilian, R
    Roth, A
    MATERIALS AND CORROSION-WERKSTOFFE UND KORROSION, 2002, 53 (10): : 727 - 739
  • [4] Surge Protection of the Reactor Coolant Pump Motors in Nuclear Power Plants
    Chang, Choong-koo
    Musyoka, Erastus Mwongela
    2021 24TH INTERNATIONAL CONFERENCE ON ELECTRICAL MACHINES AND SYSTEMS (ICEMS 2021), 2021, : 437 - 442
  • [5] Distributed Raman temperature measurement system for monitoring of nuclear power plant coolant loops
    Jensen, F
    Takada, E
    Nakazawa, M
    Kakuta, T
    Yamamoto, S
    FIBER OPTIC SENSORS V, 1996, 2895 : 132 - 143
  • [6] Parallel System Method to Improve Safety and Reliability of Nuclear Power Plants
    Xiong, Gang
    Hou, Jiachen
    Wang, Feiyue
    Nyberg, Timo R.
    Zhang, Jialin
    Fu, ManChang
    2011 9TH WORLD CONGRESS ON INTELLIGENT CONTROL AND AUTOMATION (WCICA 2011), 2011, : 237 - 242
  • [7] COOLANT FLOW RATE MEASUREMENT TECHNIQUE FOR NUCLEAR POWER REACTOR CONTROL SYSTEMS
    Davydov, R. V.
    Gureeva, I. M.
    Davydov, V. V.
    MEASUREMENT TECHNIQUES, 2022, 64 (11) : 895 - 902
  • [8] Coolant Flow Rate Measurement Technique for Nuclear Power Reactor Control Systems
    R. V. Davydov
    I. M. Gureeva
    V. V. Davydov
    Measurement Techniques, 2022, 64 : 895 - 902
  • [9] Development of Inspection System for Weld Joint between Steam Generator and Reactor Coolant Pump in Nuclear Power Plants
    Yu G.
    Zhou L.
    Tao Z.
    Zhang B.
    Hedongli Gongcheng/Nuclear Power Engineering, 2019, 40 (05): : 150 - 155
  • [10] An advanced method for determination of loss of coolant accident in nuclear power plants
    Mahmoodi, R.
    Shahriari, M.
    Zolfaghari, A.
    Minuchehr, A.
    NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (06) : 2013 - 2019
12345