Implementation of adjustable variable step based backstepping control for the PV power plant

2022 ◽  
Vol 136 ◽  
pp. 107682
Author(s):  
Asma Charaabi ◽  
Abdelaziz Zaidi ◽  
Oscar Barambones ◽  
Nadia Zanzouri
Keyword(s):  
Power Plant ◽  
Backstepping Control ◽  
Variable Step

ADAPTIVE BACKSTEPPING CONTROL OF A POWER PLANT STATION MODEL

2002 ◽  
Vol 35 (1) ◽  
pp. 215-220 ◽  
Author(s):  
Wiktor Bolek ◽  
Jerzy Sasiadek ◽  
Tadeusz Wisniewski
Keyword(s):  
Power Plant ◽  
Backstepping Control ◽  
Adaptive Backstepping ◽  
Adaptive Backstepping Control

scholarly journals On Singular Perturbation of Neutron Point Kinetics in the Dynamic Model of a PWR Nuclear Power Plant

Sci ◽  
2020 ◽  
Vol 2 (2) ◽  
pp. 30
Author(s):  
Xiangyi Chen ◽  
Asok Ray
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Singular Perturbation ◽  
Nuclear Power ◽  
Short Communication ◽  
Primary Coolant ◽  
Variable Step ◽  
Perturbed Model ◽  
Point Kinetics ◽  
Coolant System

This short communication makes use of the principle of singular perturbation to approximate the ordinary differential equation (ODE) of prompt neutron (in the point kinetics model) as an algebraic equation. This approximation is shown to yield a large gain in computational efficiency without compromising any significant accuracy in the numerical simulation of primary coolant system dynamics in a PWR nuclear power plant. The approximate (i.e., singularly perturbed) model has been validated with a numerical solution of the original set of neutron point-kinetic and thermal–hydraulic equations. Both models use variable-step Runge–Kutta numerical integration.

scholarly journals On Singular Perturbation of Neutron Point Kinetics in the Dynamic Model of a PWR Nuclear Power Plant

Sci ◽  
2020 ◽  
Vol 2 (2) ◽  
pp. 36
Author(s):  
Xiangyi Chen ◽  
Asok Ray
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Singular Perturbation ◽  
Nuclear Power ◽  
Short Communication ◽  
Primary Coolant ◽  
Variable Step ◽  
Perturbed Model ◽  
Point Kinetics ◽  
Coolant System

This short communication makes use of the principle of singular perturbation to approximate the ordinary differential equation (ODE) of prompt neutron (in the point kinetics model) as an algebraic equation. This approximation is shown to yield a large gain in computational efficiency without compromising any significant accuracy in the numerical simulation of primary coolant system dynamics in a PWR nuclear power plant. The approximate (i.e., singularly perturbed) model has been validated with a numerical solution of the original set of neutron point-kinetic and thermal–hydraulic equations. Both models use variable-step Runge–Kutta numerical integration.

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