Review on Application of Control Algorithms to Power Regulations of Reactor Cores

被引:0
作者
Li, Gang [1 ,2 ,3 ,4 ,5 ]
Wang, Xue-qian [1 ,2 ,3 ,4 ,5 ]
Liang, Bin [1 ,2 ,3 ,4 ,5 ]
Li, Xiu [1 ,2 ,3 ,4 ,5 ]
Liang, Rong-jian [1 ,2 ,3 ,4 ,5 ]
机构
[1] Tsinghua Univ, Natl Lab Informat Sci & Technol, Beijing 100084, Peoples R China
[2] Tsinghua Univ, Grad Sch Shenzhen, Shenzhen 518055, Peoples R China
[3] Tsinghua Univ, Dept Automat, Beijing 100084, Peoples R China
[4] Shenzhen Key Lab Space Robot Technol & Telesci, Shenzhen 518055, Peoples R China
[5] Shenzhen Engn Lab Precis Geometry Measurement Tec, Shenzhen 518055, Peoples R China
来源
3RD ANNUAL INTERNATIONAL CONFERENCE ON INFORMATION TECHNOLOGY AND APPLICATIONS (ITA 2016) | 2016年 / 7卷
基金
中国博士后科学基金; 国家高技术研究发展计划(863计划);
关键词
LOAD-FOLLOWING OPERATION; MODEL-PREDICTIVE CONTROL; INFINITY CONTROL-THEORY; LEVEL CONTROL DESIGN; HEAVY-WATER REACTOR; NUCLEAR-REACTORS; ROBUST-CONTROL; STEP-BACK; TEMPERATURE CONTROL; SPATIAL CONTROL;
D O I
10.1051/itmconf/20160705002
中图分类号
TP18 [人工智能理论];
学科分类号
081104 ; 0812 ; 0835 ; 1405 ;
摘要
This research is to solve the stability analysis issue of nonlinear pressurized water reactor cores. On the basis of modeling a nonlinear pressurized water reactor core using the lumped parameter method, its linearized model is achieved via the small perturbation linearization way. Linearized models of the nonlinear core at six power levels are selected as local models of this core. The T-S fuzzy idea for the core is exploited to construct the T-S fuzzy model of the nonlinear core based on the local models and the triangle membership function, which approximates the nonlinear core model within the entire range of power level. This fuzzy model as a bridge is to cater to the stability analysis of the nonlinear core after defining its stability. One stability theorem is deduced to define the nonlinear core is globally asymptotically stable in the global range of power level. Finally, the simulation work and stability analyses are separately completed. Numerical simulations show that the fuzzy model can substitute the nonlinear core model; stability analyses verify the nonlinear core is globally asymptotically stable in the global range of power level.
引用
收藏
页数:4
相关论文
共 50 条
[1]   Sliding mode control design for a PWR nuclear reactor using sliding mode observer during load following operation [J].
Ansarifar, G. R. ;
Akhavan, H. R. .
ANNALS OF NUCLEAR ENERGY, 2015, 75 :611-619
[2]   Improved temperature control of a PWR nuclear reactor using an LQG/LTR based controller [J].
Arab-Alibeik, H ;
Setayeshi, S .
IEEE TRANSACTIONS ON NUCLEAR SCIENCE, 2003, 50 (01) :211-218
[3]   An Interval Approach for Robust Control of a Large PHWR with PID Controllers [J].
Banerjee, Shohan ;
Halder, Kaushik ;
Dasgupta, Soumya ;
Mukhopadhyay, Siddhartha ;
Ghosh, Koushik ;
Gupta, Amitava .
IEEE TRANSACTIONS ON NUCLEAR SCIENCE, 2015, 62 (01) :281-292
[4]   LQG LTR ROBUST-CONTROL OF NUCLEAR-REACTORS WITH IMPROVED TEMPERATURE PERFORMANCE [J].
BENABDENNOUR, A ;
EDWARDS, RM ;
LEE, KY .
IEEE TRANSACTIONS ON NUCLEAR SCIENCE, 1992, 39 (06) :2286-2294
[5]   Robust FOPI controller design for power control of PHWR under step-back condition [J].
Bhase, S. S. ;
Patre, B. M. .
NUCLEAR ENGINEERING AND DESIGN, 2014, 274 :20-29
[6]   H∞ control theory applied to xenon control for load-following operation of a nuclear reactor [J].
Chi, SG ;
Cho, NZ .
NUCLEAR TECHNOLOGY, 2002, 137 (02) :127-138
[7]   Power level control of the TRIGA Mark-II research reactor using the multifeedback layer neural network and the particle swarm optimization [J].
Coban, Ramazan .
ANNALS OF NUCLEAR ENERGY, 2014, 69 :260-266
[8]   A trajectory tracking genetic fuzzy logic controller for nuclear research reactors [J].
Coban, Ramazan ;
Can, Burhanettin .
ENERGY CONVERSION AND MANAGEMENT, 2010, 51 (03) :587-593
[9]   Fractional order fuzzy control of nuclear reactor power with thermal-hydraulic effects in the presence of random network induced delay and sensor noise having long range dependence [J].
Das, Saptarshi ;
Pan, Indranil ;
Das, Shantanu .
ENERGY CONVERSION AND MANAGEMENT, 2013, 68 :200-218
[10]   Continuous order identification of PHWR models under step-back for the design of hyper-damped power tracking controller with enhanced reactor safety [J].
Das, Saptarshi ;
Mukherjee, Sumit ;
Das, Shantanu ;
Pan, Indranil ;
Gupta, Amitava .
NUCLEAR ENGINEERING AND DESIGN, 2013, 257 :109-127