Fuzzy-Adapted Recursive Sliding-Mode Controller Design for a Nuclear Power Plant Control

Huang, Zhengyu; Edwards, R.M.; Lee, K.Y.

doi:10.1109/tns.2004.825100

Cited by 61 publications

(15 citation statements)

References 10 publications

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“…The additional ABWR control approaches include multivariable fuzzy-logic control (FLC) and fuzzy adapted recursive sliding mode control (FARSMC) in the MS Thesis and PhD dissertation of Huang [24,25,44,48,50,55]. The adaptation of these advanced control techniques for the desired experimental validation in the HRLS is still hampered by the inability to reliability operate the loop in a stable manner; thus, a major effort was initiated to develop stability analysis of the testloop, which is expected to lead to another dissertation.…”

Section: Additional Work Peformedmentioning

confidence: 99%

Monitoring and Control Research Using a University Reactor and SBWR Test-Loop

Edwards¹

2003

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Section: Additional Work Peformedmentioning

confidence: 99%

Monitoring and Control Research Using a University Reactor and SBWR Test-Loop

Edwards¹

2003

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“…Shtessel proposed a sliding-mode plant control and state-observation strategy for space nuclear energy system TOPAZ II [21]. Huang et al gave a multi-input-multioutput (MIMO) fuzzy-adapted recursive sliding-mode plant controller for an advanced boiling water reactor (ABWR) nuclear power plant [22]. In order to achieve safe, stable, and efficient operation of the HTR-PM plant, it is necessary to give the lumped parameter model of the main plant dynamics and to propose proper plant control strategy.…”

Section: Introductionmentioning

confidence: 99%

Dynamic Modeling and Control Characteristics of the Two-Modular HTR-PM Nuclear Plant

Dong

Pan

Song

et al. 2017

Science and Technology of Nuclear Installations

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The modular high temperature gas-cooled reactor (MHTGR) is a typical small modular reactor (SMR) with inherent safety feature. Due to its high reactor outlet coolant temperature, the MHTGR can be applied not only for electricity production but also as a heat source for industrial complexes. Through multimodular scheme, that is, the superheated steam flows produced by multiple MHTGR-based nuclear supplying system (NSSS) modules combined together to drive a common thermal load, the inherent safety feature of MHTGR is applicable to large-scale nuclear plants at any desired power ratings. Since the plant power control technique of traditional single-modular nuclear plants cannot be directly applied to the multimodular plants, it is necessary to develop the power control method of multimodular plants, where dynamical modeling, control design, and performance verification are three main aspects of developing plant control method. In this paper, the study in the power control for two-modular HTR-PM plant is summarized, and the verification results based on numerical simulation are given. The simulation results in the cases of plant power step and ramp show that the plant control characteristics are satisfactory.

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“…Due to the intrinsic chattering effect of the SMC, the recursive sliding mode control (RSMC) method was introduced by Huang, Edwards and Lee to solve the chattering problem and to improve the robustness. Based on the RSMC method, a fuzzy-adapted nonlinear power-level control law was designed for the advanced boiling water reactors (ABWR) [10]. The physics-based control (PBC) method is also an effective way to design nonlinear reactor control laws by retaining or strengthening stable subdynamics and by cancelling or suppressing unstable subdynamics, which has been applied to the load-following control design for the PWRs (Pressurized Water Reactors) [11][12][13] and MHTGRs [14,15] recently.…”

Section: Introductionmentioning

confidence: 99%

“…However, these control laws have the drawback of heavy model-reliance. Some control laws needs the state prediction or observation directly based upon the reactor or SG models [9][10][11][12][14][15][16][17], and the control parameters also vary with the reactor or SG physical and thermal-hydraulic parameters [9][10][11][12][13][14][15][16][17][18], which leads to the difficulty in practically tuning and implementation. Therefore, it is necessary to develop model-free control methods to relieve the heavy model reliance of the designed control strategies.…”

Section: Introductionmentioning

confidence: 99%

Model-Free Coordinated Control for MHTGR-Based Nuclear Steam Supply Systems

Dong

2016

Energies

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Abstract:The modular high temperature gas-cooled reactor (MHTGR) is a typical small modular reactor (SMR) that offers simpler, standardized and safer modular design by being factory built, requiring smaller initial capital investment, and having a shorter construction period. Thanks to its small size, the MHTGRs could be beneficial in providing electric power to remote areas that are deficient in transmission or distribution and in generating local power for large population centers. Based on the multi-modular operation scheme, the inherent safety feature of the MHTGRs can be applicable to large nuclear plants of any desired power rating. The MHTGR-based nuclear steam supplying system (NSSS) is constituted by an MHTGR, a side-by-side arranged helical-coil once-through steam generator (OTSG) and some connecting pipes. Due to the side-by-side arrangement, there is a tight coupling effect between the MHTGR and OTSG. Moreover, there always exists the parameter perturbation of the NSSSs. Thus, it is meaningful to study the model-free coordinated control of MHTGR-based NSSSs for safe, stable, robust and efficient operation. In this paper, a new model-free coordinated control strategy that regulates the nuclear power, MHTGR outlet helium temperature and OTSG outlet overheated steam temperature by properly adjusting the control rod position, helium flowrate and feed-water flowrate is established for the MHTGR-based NSSSs. Sufficient conditions for the globally asymptotic closed-loop stability is given. Finally, numerical simulation results in the cases of large range power decrease and increase illustrate the satisfactory performance of this newly-developed model-free coordinated NSSS control law.

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Fuzzy-Adapted Recursive Sliding-Mode Controller Design for a Nuclear Power Plant Control

Cited by 61 publications

References 10 publications

Monitoring and Control Research Using a University Reactor and SBWR Test-Loop

Monitoring and Control Research Using a University Reactor and SBWR Test-Loop

Dynamic Modeling and Control Characteristics of the Two-Modular HTR-PM Nuclear Plant

Model-Free Coordinated Control for MHTGR-Based Nuclear Steam Supply Systems

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