Estimation of measurement uncertainties for subcooling margin of coolant at core outlet in CPR1000 NPPs

被引：0
|
作者：
China Nuclear Power Engineering Co. Ltd., Shenzhen [1 ]
Guangdong
518172, China
机构：
来源：
Hedongli Gongcheng | / 2卷 / 24-27期
关键词：
D O I：
10.13832/j.jnpe.2015.02.0024
中图分类号：
学科分类号：
摘要：
2
引用
收藏
相关论文
共 19 条
  • [1] Dimension of the forced vessel water level based on subcooling margin of core outlet coolant in CPR1000 nuclear power plants
    Wang Zhenying
    Li Runsheng
    Sun Kaibao
    Ma Tingwei
    [J]. INTERNATIONAL YOUTH NUCLEAR CONGRESS 2016, IYNC2016, 2017, 127 : 103 - 109
  • [2] Estimation of the Uncertainties Surrounding Measurement of Vessel Water Level in CPR1000 Nuclear Power Plants
    Wang, Zhenying
    Jiao, Zhenying
    Yu, Fengwan
    [J]. BASIC & CLINICAL PHARMACOLOGY & TOXICOLOGY, 2020, 126 : 123 - 123
  • [3] AN INVESTIGATION OF DETERMINISTIC REALISTIC METHOD FOR LBLOCA MASS AND ENERGY RELEASE EVALUATION FOR CPR1000 NPPS
    Lin, Jianshu
    Zhuang, Chengjun
    Leng, Jinzhen
    Wang, Ting
    Zhang, Zhenhua
    [J]. PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 3, 2014,
  • [4] Primary coolant drainage level response analysis and optimization of CPR1000 units
    Chen, Yongwei
    You, Dailun
    Li, Dong
    Xie, Yongjing
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2018, 327 : 1 - 6
  • [5] Analysis and application on sensitivity factors of cross validation of fill rate of CPR1000 unit reactor core coolant monitoring system
    Chen, Yongwei
    Xie, Yongjing
    Wang, Zuo
    Luan, Zhenhua
    Ling, Jun
    [J]. ANNALS OF NUCLEAR ENERGY, 2019, 133 : 649 - 657
  • [6] Accident tolerant fuel thermal hydraulic behaviors evaluation during loss of coolant accident in CPR1000
    Yu, Honghao
    Chen, Zhijie
    Cai, Jiejin
    [J]. ANNALS OF NUCLEAR ENERGY, 2020, 139
  • [7] Research on 90° elbow structure optimization for main coolant piping of CPR1000 nuclear power plant
    [J]. Li, Q.-B., 1600, Atomic Energy Press (34):
  • [8] Improvement of core control strategy for CPR1000: Load follow without boron adjustment
    Zhang, Yawei
    Wang, Pengfei
    Zhao, Fuyu
    Li, Gang
    [J]. PROGRESS IN NUCLEAR ENERGY, 2015, 81 : 98 - 103
  • [9] Mechanical Shim core operational strategy designed for CPR1000 nuclear power plant
    Zhang, Y. W.
    Zeng, W. J.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2017, 322 : 14 - 26
  • [10] Dynamic simulation and control studies of CPR1000 reactor core with advanced MSHIM control strategy
    Song, Hongbing
    Wan, Jiashuang
    Luo, Run
    Zhao, Fuyu
    [J]. PROGRESS IN NUCLEAR ENERGY, 2018, 105 : 29 - 41
12