Nuclear plant models for medium- to long-term power system stability studies

Inoue, Taiki; Ichikawa, Tatsumi; Kundur, P.; Hirsch, P.

doi:10.1109/59.373936

Cited by 23 publications

(10 citation statements)

References 4 publications

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“…The steam bypass control system of a nuclear power unit acts when there is a large deviation between a nuclear turbine's power output of the primary circuit and the secondary circuit, which is an important control method to ensure the safety of the reactor [17]. Figure 6 shows the mathematical model of the steam bypass control system under a transient condition.…”

Section: Steam Bypass Control System Modelmentioning

confidence: 99%

“…Considering the main equipment, subsystem boundary [23], and operating characteristics, the PWR primary loop system model was divided into multiple sub-modules adopting the modular modeling method [17,24]. Figure 8 shows the model of the nuclear power unit reactor core system.…”

Section: Reactor Core System Modelmentioning

confidence: 99%

“…However, in order to stabilize the unit and grid frequency, it is necessary to establish the prime mover and its speed control system model considering frequency protection [14,15]. Much research has focused on second-generation NPP modeling suitable for different simulation time scales, including the full range simulator, comprehensive simulation program, or mathematical methods [16][17][18][19][20]. This has mainly analyzed the characteristics of overspeed protection from the perspective of the speed-governing system, but has rarely deeply analyzed the response characteristics of the reactor core system under large disturbances [21].…”

Section: Introductionmentioning

confidence: 99%

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A Speed-Governing System Model with Over-Frequency Protection for Nuclear Power Generating Units

Wang

Sun²,

Zhao

et al. 2019

Energies

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Overspeed is more likely to occur in the process of load rejection or large disturbances for nuclear steam turbines due to the large parameter range and low steam parameters, as well as the power of the low-pressure cylinder accounting for a high proportion of the total power. It is of great significance to study the overspeed characteristics of nuclear power plants (NPPs) to ensure the safe and stable operation of the unit and power grid. According to the characteristics of NPPs, the overspeed protection model and the super-acceleration protection model were established, which were added to the speed-governing system model. The response characteristics of the reactor, thermal system, steam turbine and speed-governing system in the process of load rejection or large disturbances of the power grid were analyzed and simulated. The results were compared using the simulation software personal computer transient analyzer (PCTRAN). The simulation results showed that quickly closing both the high and medium pressure regulating valves could effectively realize frequency control when load rejection or a large grid disturbance occurred. The over-acceleration protection cooperates with the super-acceleration protection to avoid the repeated opening/closing of the valves due to overspeed protection. This could effectively reduce the impact of large disturbances on the reactor, thermal system, and turbine.

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Section: Steam Bypass Control System Modelmentioning

confidence: 99%

Section: Reactor Core System Modelmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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A Speed-Governing System Model with Over-Frequency Protection for Nuclear Power Generating Units

Wang

Sun²,

Zhao

et al. 2019

Energies

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“…Some approaches for modeling of nuclear plant dynamics for power system long-term dynamics have been presented in previous studies [2]- [4]. These models, however, are generally simple, the coolant pump, rapid closing mechanism, bypass valve control, protection system not taken into account .…”

Section: Nuclear Power Plant Model Based On Pwrmentioning

confidence: 99%

Research and Analyse for Pressurized Water Reactor Plant into Power System Dynamics Simulation

Xiong

Liu

Shi

et al. 2009

2009 Asia-Pacific Power and Energy Engineering Conference

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The nuclear power plants are being constructed and operated widely in recent years. Consequently, it is necessary to study nuclear power plants (NPPs) dynamic characteristics and power system dynamics simulations with nuclear plant after NPPs has been introduced into power system. At first, the paper presents functional description of NPP. Then a detailed and new models of generating plant with PWR have been developed in PSASP through user-defined modeling program for mediumterm and long-term power system transient stability analyse. In the end, the results for power system dynamics simulation with nuclear plant are presented. Keywords-nuclear power plant; pressurized water reactor; model; power systemI.

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“…The transient analysis of interactions among different systems has been considered by a few studies in nuclear engineering literature. In the earliest works [2][3][4], the protection of nuclear power plants has been discussed; however, the mutual influences between the nuclear power plants, grid, and their protection systems have not been sufficiently considered. The conventional models of nuclear power plants proposed therein have high computational complexities, which further limited their suitability in large-scale power system dynamic simulations.…”

Section: Introductionmentioning

confidence: 99%

Analysis of Transient Interactions between a PWR Nuclear Power Plant and a Faulted Electricity Grid

2021

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This paper presents the transient stability analysis of a pressurised water-type nuclear power plant following faults and disturbances affecting the electricity grid to which it is connected. The modelled nuclear plant consists of various integrated subsystems, such as core neutronics and thermal-hydraulics, piping and plenum, pressuriser, steam generator, turbine, governor, and dynamics shaft, in addition to the turbine-speed controller. The nonlinear nuclear power plant model is linearised at the operating point to acquire a linear model for controller design. The turbine-speed control loop effectively enacts a closed-loop implementation of the nuclear power plant connected to the electric grid. The various transient stability enhancement components such as the power system stabiliser, static var compensator, and static synchronous compensator are employed to test performance during severe contingencies. The interaction between the nuclear power plant, electric grid, and protection system is studied under various scenarios such as single-phase fault, three-phase fault, and permanent load loss. The performance of the nonlinear plant is further observed during load-following operation. The dynamic behaviour of the overall system is analysed using simulations in the MATLAB/Simulink/Simscape environment.

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Nuclear plant models for medium- to long-term power system stability studies

Cited by 23 publications

References 4 publications

A Speed-Governing System Model with Over-Frequency Protection for Nuclear Power Generating Units

A Speed-Governing System Model with Over-Frequency Protection for Nuclear Power Generating Units

Research and Analyse for Pressurized Water Reactor Plant into Power System Dynamics Simulation

Analysis of Transient Interactions between a PWR Nuclear Power Plant and a Faulted Electricity Grid

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