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

被引：3
|
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
来源：
ANNALS OF NUCLEAR ENERGY | 2023年 / 186卷
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
  • [21] Control approach to the load frequency regulation of a Generation IV Lead-cooled Fast Reactor
    Ponciroli, Roberto
    Cammi, Antonio
    Lorenzi, Stefano
    Luzzi, Lelio
    ENERGY CONVERSION AND MANAGEMENT, 2015, 103 : 43 - 56
  • [22] Feasibility study of a passive DHR system with heat transfer enhancement mechanism in a lead-cooled fast reactor
    Eoh, Jae-Hyuk
    Kim, Seyun
    Kim, Sang-Ji
    Kim, Seong-O
    NUCLEAR TECHNOLOGY, 2007, 160 (02) : 216 - 232
  • [23] Core design investigation for a SUPERSTAR small modular lead-cooled fast reactor demonstrator
    Bortot, S.
    Moisseytsev, A.
    Sienicki, J. J.
    Artioli, Carlo
    NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (08) : 3021 - 3031
  • [24] Low-power lead-cooled fast reactor loaded with MOX-fuel
    Sitdikov, E. R.
    Terekhova, A. M.
    INTERNATIONAL CONFERENCE FOR YOUNG SCIENTISTS, SPECIALISTS, AND POSTGRADUATES ON NUCLEAR REACTOR PHYSICS 2016 (ICNRP-2016), 2017, 781
  • [25] Core design of long-cycle small modular lead-cooled fast reactor
    Tung Dong Cao Nguyen
    Choe, Jiwon
    Ebiwonjumi, Bamidele
    Lemaire, Matthieu
    Lee, Deokjung
    INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2019, 43 (01) : 254 - 273
  • [26] Development and application of CFD and subchannel coupling analysis code for lead-cooled fast reactor
    Wang, Chi
    Cao, Liankai
    Zhang, Xuebei
    Shen, Chong
    Chen, Hongli
    INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2019, 43 (14) : 8447 - 8462
  • [27] A Control-Oriented Modeling Approach to Spatial Neutronics Simulation of a Lead-Cooled Fast Reactor
    Lorenzi, S.
    Cammi, A.
    Luzzi, L.
    Ponciroli, R.
    JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE, 2015, 1 (03):
  • [28] Neutronic investigation of ALFRED lead-Cooled fast reactor core using monte carlo modeling
    Ganjaroodi, Saeed Zare
    Zarifi, Ehsan
    ATOMIC ENERGY, 2023, 134 (3-4) : 264 - 274
  • [29] MBSE-based passive residual heat removal system for lead-cooled fast reactors design requirement analysis
    Tang M.
    Zhao P.
    Li W.
    Wang K.
    He Jishu/Nuclear Techniques, 2024, 47 (04):
  • [30] Comparative neutronic study of homogeneous and heterogeneous thorium fuel based core design in a lead-cooled fast reactor
    Juarez-Martinez, Luis-Carlos
    Francois, Juan-Luis
    ANNALS OF NUCLEAR ENERGY, 2018, 114 : 102 - 109
12345