AP1000 PLANT TYPICAL OPERATIONAL TRANSIENT ANALYSIS

被引：0
|
作者：
Liu Lixin [1 ]
Zheng Limin [1 ]
机构：
[1] Shanghai Nucl Engn Res & Design Inst, Shanghai 200233, Peoples R China
来源：
PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 1 | 2014年
关键词：
PWR; Pressurizer; URD; Step/Ramp load; Load rejection; Operational transient;
D O I：
暂无
中图分类号：
TH [机械、仪表工业];
学科分类号：
0802 ;
摘要：
According to advanced light water reactor (ALWR) Utility Requirement Document (URD), plant control systems should be designed to meet the specified design requirements for an advanced 1000 MWe class PWR nuclear power plant (NPP). As per the plant design requirements, AP 1000 control systems were simulated, and plant thermal-hydraulic performance analysis have been performed with RELAP5 thermal-hydraulic computer code under five typical operational transients, i.e. (a) a step load increase from 15% FP to 25%FP, (b) a step load decrease from 100% FP to 90%FP, (c) +5%/min ramp load increase, (d) large load rejection to house load at full power, (e) normal reactor trip at full power. Based on a preliminary plant performance analysis, it indicates that plant design requirements could be satisfied for AP1000 control systems.
引用
收藏
页数：8
相关论文
共 50 条
  • [31] Study on Schedule Control in AP1000 Nuclear Plant Project
    Fang Xiaopeng
    [J]. PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING 2010, VOL 6, 2011, : 181 - 186
  • [32] LEARNING THROUGH DELIVERY, WESTINGHOUSE AP1000® PLANT LICENSING
    Gorgemans, Julie
    Corletti, Michael M.
    DeLong, Richard A.
    Schulz, Terry L.
    [J]. PROCEEDINGS OF THE 22ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2014, VOL 1, 2014,
  • [33] Analysis of passive residual heat removal system in AP1000 nuclear power plant
    Sierchula, J.
    [J]. INTERNATIONAL CONFERENCE ON THE SUSTAINABLE ENERGY AND ENVIRONMENTAL DEVELOPMENT, 2019, 214
  • [34] Analyses of liquid entrainment through ADS-4 in AP1000 during a typical small break LOCA transient
    Wang, W. W.
    Su, G. H.
    Meng, Z. M.
    Tian, W. X.
    Qiu, S. Z.
    [J]. ANNALS OF NUCLEAR ENERGY, 2013, 60 : 195 - 201
  • [35] Sensitivity Analysis of Relap5 Simulation on AP1000 Nuclear Power Plant
    谢明亮
    谢飞
    单福昌
    谢政权
    [J]. Journal of Donghua University(English Edition), 2018, 35 (01) : 94 - 100
  • [36] Study on Transient Performance in Loss of Coolant Accident for AP1000 SFP
    Duan Y.
    He X.
    Jing F.
    Cai Z.
    Yu X.
    [J]. Hedongli Gongcheng/Nuclear Power Engineering, 2019, 40 (01): : 147 - 151
  • [37] AP1000 Design Certification
    不详
    [J]. NUCLEAR PLANT JOURNAL, 2006, 24 (01) : 14 - 14
  • [38] AP1000 design approval
    不详
    [J]. NUCLEAR ENGINEERING INTERNATIONAL, 2006, 51 (618): : 3 - 3
  • [39] AP1000核岛封顶
    [J]. 中国核工业, 2013, (04) : 36 - 37
  • [40] AP1000: set to compete
    Paulson, CK
    [J]. NUCLEAR ENGINEERING INTERNATIONAL, 2002, 47 (579): : 20 - 22
12345