A modeling error compensation approach for the feedback control of the nuclear reactor operation

被引:4
作者
Alvarez-Ramirez, Jose [1 ]
Espinosa-Paredes, Gilberto [1 ]
机构
[1] Univ Autonoma Metropolitana Iztapalapa, Div Ciencias Basicas & Ingn, Mexico City 09340, DF, Mexico
关键词
Nuclear reactor control; BWR; Lumped model; Reduced-order model; Modeling-error compensation; BOILING WATER-REACTORS; REDUCED-ORDER MODEL; NONLINEAR DYNAMICS; POWER; STABILITY; PWR; DESIGN;
D O I
10.1016/j.nucengdes.2021.111394
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
Nuclear energy for civil applications has been a matter of renewed interest as it offers clean, safe, and reliable energy sources. A new generation of compact reactors and improved safety strategies have driven refreshed research on the design and control of nuclear plants. New results on the regulation of the power output of nuclear reactors should provide improved operation strategies oriented to reliability and safety. The present work aims to study the stability and performance of a nuclear reactor under nonlinear feedback control actions. The study considered the five states March-Leuba mathematical model of a boiling water reactor. A nonlinear feedback controller that leads to exact cancellation of nonlinearities was obtained by dynamical inversion methods. However, uncertain parameters and unmeasured signals are commonly found in practical conditions. To address this issue, an observed-based estimation scheme was proposed to obtain estimates of the unmeasured signals and the trajectory of the modeling error, which are subsequently used to obtain an approximate version of the exact feedback inversion. Numerical simulations for open-loop stable and unstable (e.g., large-amplitude limit cycle) showed that the proposed control scheme provides closed-loop stability despite large model uncertainties.
引用
收藏
页数:9
相关论文
共 24 条
[1]  
Alvarez-Ramírez J, 1999, INT J ROBUST NONLIN, V9, P361, DOI 10.1002/(SICI)1099-1239(199905)9:6<361::AID-RNC411>3.0.CO
[2]  
2-U
[3]  
[Anonymous], 1983, T 1983 WINT M AM NUC
[4]   Sliding mode observer design for a PWR to estimate the xenon concentration & delayed neutrons precursor density based on the two point nuclear reactor model [J].
Ansarifar, G. R. ;
Esteki, M. H. ;
Arghand, M. .
PROGRESS IN NUCLEAR ENERGY, 2015, 79 :104-114
[5]   Application of a reduced order model to BWR corewide stability analysis [J].
Ceceñas-Falcón, M ;
Edwards, RM .
ANNALS OF NUCLEAR ENERGY, 2001, 28 (12) :1219-1235
[6]   Disturbance-Observer-Based Control and Related Methods-An Overview [J].
Chen, Wen-Hua ;
Yang, Jun ;
Guo, Lei ;
Li, Shihua .
IEEE TRANSACTIONS ON INDUSTRIAL ELECTRONICS, 2016, 63 (02) :1083-1095
[7]   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
[8]   History review of nuclear reactor safety [J].
Gu, Zhixing .
ANNALS OF NUCLEAR ENERGY, 2018, 120 :682-690
[9]   Design of a fault tolerated intelligent control system for a nuclear reactor power control: Using extended Kalman filter [J].
Hatami, Ehsan ;
Salarieh, Hassan ;
Vosoughi, Naser .
JOURNAL OF PROCESS CONTROL, 2014, 24 (07) :1076-1084
[10]   Fuzzy adaptive backstepping load following control for MHTGRs with power error constraint and output disturbances [J].
Hui, Jiuwu ;
Ling, Jun ;
Yuan, Jingqi .
ANNALS OF NUCLEAR ENERGY, 2021, 154