Control of the reactor core power in PWR using optimized PID controller with the real-coded GA

Mousakazemi, Seyed Mohammad Hossein; Ayoobian, Navid; Ansarifar, G.R.

doi:10.1016/j.anucene.2018.03.038

Cited by 57 publications

(29 citation statements)

References 33 publications

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“…The particle swarm optimization approach has been implemented to find the gains of the robust PID adaptive controller for exoskeletons (Belkadi, Oulhadj, Touati, Safdar, Khan, & Daachi, Belkadi et al, 2017). A real-coded genetic algorithm has been applied for optimal design of the PID control for a reactor (Mousakazemi et al, 2018). A whale optimization algorithm has been suggested to tune proportional-integral-derivative controllers and utilized for AVR systems (Mosaad et al, 2019).…”

Section: Introductionmentioning

confidence: 99%

Optimal design of an adaptive robust proportional-integral-derivative controller based upon sliding surfaces for under-actuated dynamical systems

2021

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This paper presents a novel adaptive robust proportional-integralderivative (PID) controller for under-actuated dynamical systems via employing the advantages of the PID control and sliding surfaces. The related control gains as adjustable parameters are computed during the control process using gradient descent techniques and the chain derivative rule. Based on the design of control rules, the genetic algorithm optimization is utilized in order to find the optimal values of the learning rates and initial conditions of the control gains. The suggested strategy is implemented successfully to stabilize the cart-pole and ball-beam systems. Lastly, the simulation results demonstrate the efficacy of the proposed controller to control such under-actuated dynamical systems as well as its superiority in comparison with other recently introduced methods.

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Section: Introductionmentioning

confidence: 99%

Optimal design of an adaptive robust proportional-integral-derivative controller based upon sliding surfaces for under-actuated dynamical systems

2021

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“…erefore, recently some researches focused on the control algorithm of reactor power have already been conducted [4][5][6]. ere are many research achievements on the improvement of PID algorithm so far, focusing on the optimization of PID parameters, such as Genetic Algorithm [7][8][9], Particle Swarm Optimization [10][11][12], T-S fuzzy identification [10], adaptive PID [13], and other methods, to improve the control performance of PID controller. Another research direction is to use predictive control for PWR reactor power control, mainly to improve the performance of predictive control.…”

Section: Introductionmentioning

confidence: 99%

Design and Verification of Reactor Power Control Based on Stepped Dynamic Matrix Controller

Zhang

Deng

et al. 2019

Science and Technology of Nuclear Installations

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As key equipment in nuclear power plant, the reactor power control system is adopted to strictly control and regulate the reactor power of a PWR (pressurized water reactor) in a nuclear power plant. A well-optimized predictive control algorithm based on SDMC (stepped dynamic matrix controller) is developed and introduced in this paper and applied to the power regulation of a reactor power model. In addition, the test and verification of this application is conducted by two different methods and devices: the virtual verification platform and the physical DCS (digital control system). The result of the verification suggests that the application of SDMC gains a better performance in the maximum dynamic deviation, adjustment time, overshoot, and so on.

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“…This paper discusses the plant dynamics of the one-pass core cooling-type SCW fast reactor. Type of PID-like controllers is applied as it was successfully applied in nuclear reactors [15], [16], [23], [24]. Applicability of the controller type in controlling operating parameters of power, steam temperature, and pressure of the SCW fast reactor regarding the adoption of the one-pass core cooling-type is discussed.…”

Section: Introductionmentioning

confidence: 99%

Control System of a Super Fast Reactor with Single Flow Pass Core

Sutanto¹,

2018

Int. J. Adv. Sci. Eng. Inf. Technol.

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The one-pass supercritical pressure light water fast reactor has different core structure from that of the two-pass cooling type one. The distance between inlet and outlet channels of the one-pass supercritical pressure light water fast reactor is shorter with less core water inventory due to the removal of the gap channels. Its responses to a perturbation are similar to those of the two-pass core. However, change of the outlet temperature regarding to a perturbation of power to flow ratio in the one-pass cooling type fast reactor is larger. It is important to suppress the change as small as possible to keep the integrity of the reactor structure. Early designs of power and pressure control systems of a supercritical pressure light water fast reactor are applicable to control the power and pressure parameters, but it is not for the early outlet temperature control system that considered only the outlet temperature deviation as the feedback. An improved outlet temperature control system that considers both the signals of outlet temperature and power deviations as the control feedbacks can be applied in the one-pass cooling-type fast reactor with adjustment on the control's parameters. Optimized control's parameters can suppress the change of the outlet temperature significantly without oscillation. By using the control system, responses of the one-pass supercritical pressure light water fast reactor to the designated perturbations satisfy the criteria.

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Control of the reactor core power in PWR using optimized PID controller with the real-coded GA

Cited by 57 publications

References 33 publications

Optimal design of an adaptive robust proportional-integral-derivative controller based upon sliding surfaces for under-actuated dynamical systems

Optimal design of an adaptive robust proportional-integral-derivative controller based upon sliding surfaces for under-actuated dynamical systems

Design and Verification of Reactor Power Control Based on Stepped Dynamic Matrix Controller

Control System of a Super Fast Reactor with Single Flow Pass Core

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