Design and development of the power regulation system for lead-cooled fast reactor based on system modeling and fuzzy algorithm

被引:5
|
作者
Shen, Yanyi [1 ]
Dong, Sifan [1 ]
Tang, Junjie [1 ]
Chen, Hongli [1 ]
机构
[1] Univ Sci & Technol China, Sch Nucl Sci & Technol, Hefei 230026, Peoples R China
关键词
Lead-cooled fast reactor; Reactor power regulation system; Fuzzy PID controller; RELAP5; Visualization and simulation platform; PID CONTROLLER;
D O I
10.1016/j.anucene.2023.109734
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The study on reactor power regulation system for lead-cooled fast reactor (LFR) is conducive to advancing the achievement of the LFR nuclear power plants (NPPs). This paper aims to explore the feasible power control strategy for LFR to achieve reactor power regulation rapidly and stably in normal operation. RELAP5 is used to build a detailed LFR model and the C++ language is adopted for design and optimization of the power regulation system based on PID controller and fuzzy algorithm, respectively. The simulation is implemented and verified in the visualization and simulation platform for lead-cooled fast reactor (KMC-VSPLFR). The coupling effect be-tween the reactor power and the coolant temperature for LFR is solved by the coolant temperature control module of the RAPRS. Typical load change conditions and interferences are applied to test and verify the control performance and the anti-disturbance capability of RAPRS, and the robustness is demonstrated.
引用
收藏
页数:12
相关论文
共 50 条
  • [41] Lead-cooled system design and challenges in the frame of Generation IV International Forum
    Cinotti, Luciano
    Smith, Craig F.
    Sekimoto, Hiroshi
    Mansani, Luigi
    Reale, Marco
    Sienicki, James J.
    JOURNAL OF NUCLEAR MATERIALS, 2011, 415 (03) : 245 - 253
  • [42] SIMULATION MODEL OF A PASSIVE DECAY HEAT REMOVAL SYSTEM FOR LEAD-COOLED FAST REACTORS
    Damiani, Lorenzo
    Prato, Alessandro Pini
    INTERNATIONAL MECHANICAL ENGINEERING CONGRESS AND EXPOSITION - 2012, VOL 6, PTS A AND B, 2013, : 1273 - 1280
  • [43] Development and Performance Analysis of an Electromagnetic Pump for a Thermal Hydraulic Experimental Loop of a Lead-Cooled Fast Reactor
    Li, Zi'ang
    Yuan, Lanfei
    Wang, Chenglong
    Qiu, Suizheng
    Li, Ying
    ENERGIES, 2025, 18 (03)
  • [44] Simulation Model of a Passive Decay Heat Removal System for Lead-Cooled Fast Reactors
    Damiani, Lorenzo
    Prato, Alessandro Pini
    JOURNAL OF ENGINEERING FOR GAS TURBINES AND POWER-TRANSACTIONS OF THE ASME, 2015, 137 (03):
  • [45] Sub-channel-based multiscale thermal-hydraulic analysis of a medium-power, lead-cooled fast reactor
    Cao, Liankai
    Zhang, Xilin
    Chen, Hongli
    INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2020, 44 (07) : 5305 - 5319
  • [46] Optimization of supercritical nuclear power system based on sodium cooled fast reactor
    Zhao, Zhenxing
    Liao, Mengran
    Wei, Wei
    Wu, Jun
    Wang, Wei
    THIRD INTERNATIONAL CONFERENCE ON ENERGY ENGINEERING AND ENVIRONMENTAL PROTECTION, 2019, 227
  • [47] Analysis of operator support method based on intelligent dynamic interlock in lead-cooled fast reactor simulator
    Xu, Peng
    Wang, Jianye
    Yang, Minghan
    Wang, Weitian
    Bai, Yunqing
    Song, Yong
    ANNALS OF NUCLEAR ENERGY, 2017, 99 : 279 - 282
  • [48] Development and application of a multi-physics and multi-scale coupling program for lead-cooled fast reactor
    Xiao Luo
    Chi Wang
    Ze-Ren Zou
    Lian-Kai Cao
    Shuai Wang
    Zhao Chen
    Hong-Li Chen
    Nuclear Science and Techniques, 2022, 33
  • [49] Development and verification of lead-bismuth cooled fast reactor calculation code system Mosasaur
    Zhang, Bin
    Wang, Lianjie
    Lou, Lei
    Zhao, Chen
    Peng, Xingjie
    Yan, Mingyu
    Xia, Bangyang
    Zhang, Ce
    Qiao, Liang
    Wu, Qu
    FRONTIERS IN ENERGY RESEARCH, 2023, 10
  • [50] Development and application of a multi-physics and multi-scale coupling program for lead-cooled fast reactor
    Xiao Luo
    Chi Wang
    Ze-Ren Zou
    Lian-Kai Cao
    Shuai Wang
    Zhao Chen
    Hong-Li Chen
    Nuclear Science and Techniques, 2022, 33 (02) : 42 - 54