Saturated Output Feedback Dissipation Steam Temperature Control for the OTSG of MHTGRs

Dong, Zhe; Huang, Xiaojin; Liangju, Zhang

doi:10.1109/tns.2011.2142192

Cited by 16 publications

(9 citation statements)

References 27 publications

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“…There have been many process control system design approaches such as the relative gain analysis-(RGA-) based method. In this paper, both the feedback loops and control laws of HTR-PM control system are designed by the use of the physicsbased NSSS control method proposed in [30][31][32][33][34][35][36] and module coordination control method proposed in [28,29], which provide the globally asymptotic closed-loop stability through guaranteeing the convergence of Lyapunov functions determined by the shifted-ectropies of neutron kinetics and thermodynamics as well as the kinetic energy stored in secondary-loop FFN.…”

Section: Control Design Methodmentioning

confidence: 99%

“…, 5 and < ) is the length between points and in Figure 4, and s , s , ℎ s s , and s are, respectively, the flow density (kg/m 3 ), flowrate (kg/s), enthalpy per unit mass (J/kg), heat flux from the primary side, and cross section (m 2 ) of node of the secondary side. Here, 13 is the length of the subcooled section, 35 is that of the boiling section, and ℎ 1s is specific enthalpy of the feedwater. Due to the high speed of the steam flow, it is assumed that…”

Section: Secondary Sidementioning

confidence: 99%

“…To improve both the steady and transient performance, it is necessary to give proper control laws for the NSSS module composed of the MHTGR and OTSG by considering the nonlinear dynamics. The physics-based control (PBC) method is 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 PWR [30,31], MHTGR [32][33][34], and OTSG [35]. Very recently, based upon the PBC method, a novel model-free MHTGR-based NSSS module control strategy was proposed in [36], which provides globally asymptotic stability (GAS) for the NSSS module if the feedwater temperature is constant and both the helium and feedwater flowrate are well regulated.…”

Section: Nsss Module Controlmentioning

confidence: 99%

See 2 more Smart Citations

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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Section: Control Design Methodmentioning

confidence: 99%

Section: Secondary Sidementioning

confidence: 99%

Section: Nsss Module Controlmentioning

confidence: 99%

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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

Self Cite

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“…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. From the aspect of SG controller design, some advanced control approaches such as the model predictive control (MPC) [16], neurofuzzy [17] and feedback-dissipation [18] methods have all been applied to improve the regulation performance of SGs.…”

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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Control system design for the once-through steam generator of lead–bismuth cooled reactor based on classical control theory

Wan

Xie

Wang

et al. 2022

Annals of Nuclear Energy

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Saturated Output Feedback Dissipation Steam Temperature Control for the OTSG of MHTGRs

Cited by 16 publications

References 27 publications

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

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

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

Control system design for the once-through steam generator of lead–bismuth cooled reactor based on classical control theory

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