Sliding Mode Control for Spatial Stabilization of Advanced Heavy Water Reactor

Munje, Ravindra; Patre, B. M.; Shimjith, S. R.; Tiwari, A.P.

doi:10.1109/tns.2013.2264635

Cited by 50 publications

(32 citation statements)

References 31 publications

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“…Hence, periodic output feedback (POF)-based controller for three-time-scale system of AHWR is presented in [26] with a sampling period of 2 s. Although MROF-based controllers (i.e., FOS and POF) give a very simple control structure, they lack robustness and may not work satisfactorily in the presence of disturbance, parameter variations, and perturbation in operating conditions. Hence, a single-input fuzzy logic controller [27] and robust continuous-time SMC (CSMC) [28] are proposed for spatial control of AHWR. In [28], AHWR system is decoupled into slow and fast subsystems by two-stage decomposition and CSMC is designed using merely slow subsystem states.…”

Section: Brief Overview Of Ahwrmentioning

confidence: 99%

“…Hence, a single-input fuzzy logic controller [27] and robust continuous-time SMC (CSMC) [28] are proposed for spatial control of AHWR. In [28], AHWR system is decoupled into slow and fast subsystems by two-stage decomposition and CSMC is designed using merely slow subsystem states. The 17 node model of the AHWR, given by the set of (1)-(7) represents the neutronics and thermal hydraulic behavior of the core reasonably, i.e., there is always some uncertainty in values of coupling coefficients (α j i and α ii ) and the coefficients appearing in (6) and (7).…”

Section: Brief Overview Of Ahwrmentioning

confidence: 99%

“…This controller is applied to the nonlinear system of AHWR and the simulation results are generated. These results are compared with the CSMC technique presented in [28] and DSMC obtained by two-stage decomposition.…”

Section: Brief Overview Of Ahwrmentioning

confidence: 99%

See 2 more Smart Citations

Discrete-Time Sliding Mode Spatial Control of Advanced Heavy Water Reactor

Munje¹,

Patre²,

Tiwari

2016

IEEE Trans. Contr. Syst. Technol.

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This brief presents the design of a discrete-time sliding mode control (DSMC) for spatial power stabilization of advanced heavy water reactor (AHWR). Mathematical model of AHWR is represented by 90 first-order nonlinear differential equations with 18 outputs and five inputs. The linear model is obtained by linearizing nonlinear equations over the rated power. This linear model is found to be highly ill conditioned and is possessing three-time-scale property. Initially, the linear model is transformed into block diagonal form to separate slow, fast 1, and fast 2 subsystems and then DSMC is designed using slow subsystem alone since fast 1 and fast 2 subsystems are stable. The proposed DSMC strategy is designed using the constant plus proportional rate reaching law with matched disturbance. Finally, the nonlinear multivariable model of AHWR is simulated with the designed controller and the results are generated under different transients. The efficacy of the proposed DSMC is demonstrated with the comparison of prevalent controllers in the literature and the performance is evaluated under the same transient levels.Index Terms-Advanced heavy water reactor (AHWR), composite control, discrete-time sliding mode control (DSMC), global power control in large reactors, reaching law, spatial control.

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Section: Brief Overview Of Ahwrmentioning

confidence: 99%

Section: Brief Overview Of Ahwrmentioning

confidence: 99%

See 1 more Smart Citation

Discrete-Time Sliding Mode Spatial Control of Advanced Heavy Water Reactor

Munje¹,

Patre²,

Tiwari

2016

IEEE Trans. Contr. Syst. Technol.

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“…Reddy et al [34] contrived a PWR core spatial power control system by the use of the sliding mode control and a core state observer. The spatial power distribution control system of an advanced heavy water reactor core was achieved by Munje et al [35] based on the sliding mode control.…”

Section: H-infinity Robust Controlmentioning

confidence: 99%

“…Improving power regulation technology of cores by the introduction of control algorithms is an important measure for safety and availability of NPPs. Over the decades, many control algorithms have been exploited and applied by researchers to core power regulations, which are the stateor output-feedback control with a state observer [2][3][4][5][6][7][8][9][10][11][12][13][14][15][16][17], the optimal control [18,19], the neural network or fuzzy intelligent control [20][21][22][23][24][25], the model predictive control [26][27][28], the H ∞ robust control [29][30][31], the sliding model control [32][33][34][35], the fractional order control [36][37][38][39][40][41] and other control algorithms [42][43][44][45][46][47]…”

Section: Introductionmentioning

confidence: 99%

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

Wang

Liang

et al. 2016

ITM Web Conf.

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Abstract. 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.

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Adaptive fuzzy sliding mode control based on Takagi‐Sugeno techniques for power tracking in nuclear reactor

Zhang

2018

IEEJ Transactions Elec Engng

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Reactor power control is one of the most significant problems in a nuclear power plant. An innovative adaptive fuzzy sliding mode control (AFSMC) based on Takagi‐Sugeno techniques for power tracking in nuclear reactor is presented. The developed fuzzy model has considered both neutron dynamics and thermal hydraulic dynamics. By using a fuzzy sliding surface, the AFSMC ensures asymptotical stability and also reduces the input chattering. Moreover, adaptive techniques are used to estimate the upper bound of uncertainties and disturbances. To validate the proposed controller, simulations are performed and compared between AFSMC and three other methods, and results show that the effectiveness of the proposed controller can be confirmed. © 2018 Institute of Electrical Engineers of Japan. Published by John Wiley & Sons, Inc.

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Sliding Mode Control for Spatial Stabilization of Advanced Heavy Water Reactor

Cited by 50 publications

References 31 publications

Discrete-Time Sliding Mode Spatial Control of Advanced Heavy Water Reactor

Discrete-Time Sliding Mode Spatial Control of Advanced Heavy Water Reactor

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

Adaptive fuzzy sliding mode control based on Takagi‐Sugeno techniques for power tracking in nuclear reactor

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