Numerical analysis of transient pressure variation in the condenser of a nuclear power station

Wang, Xinjun; Zhou, Zijie; Song, Zhao; Lu, Qiankui; Li, Jiafu

doi:10.1007/s12206-016-0149-y

Cited by 8 publications

(3 citation statements)

References 4 publications

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“…When a nu clear power plant is in nor mal work ing con di tions, the pres sure of the con denser needs to be main tained at a low and sta ble level. In this way the con denser can pro vide low and sta ble back pres sure for the steam tur bine to en sure the ef fi ciency and sta bil ity of the plant [9,10]. The ex ist ing pres sure con trol system of the con denser gen er ally adopts PI con trol method.…”

Section: Condenser Pressure Control Systemmentioning

confidence: 99%

Optimal design of a nuclear power plant condenser control system based on multi-objective optimization algorithm

Chen

et al. 2020

NUCL TECH RAD PROT

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A condenser control system of a nuclear power plant consists of a pressure control system, a condensate water sub-cooling degree control system and a water level control system. The existing control optimization methods can hardly take into account all the performance indices of the three control systems at the same time. To solve this problem, this paper presents a control optimization method based on a multi-objective optimization algorithm. This method takes control parameters as optimization objects, and takes the performance of step response as optimization objectives. The multi-objective particle swarm optimization algorithm based on Pareto dominance concept is used to solve the optimization problem. This enables obtaining of high-quality control parameters. Simulation results confirm the feasibility and effectiveness of this control optimization method.

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Section: Condenser Pressure Control Systemmentioning

confidence: 99%

Optimal design of a nuclear power plant condenser control system based on multi-objective optimization algorithm

Chen

et al. 2020

NUCL TECH RAD PROT

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“…Jiang and Ding [16] studied the pressure changes of a condenser under design conditions and summer conditions when all cooling water was lost. Wang and Zhou [17] constructed a mathematical model for transient heat transfer and pressure in a circulating cooling water system and condenser. Through numerical investigation, it was observed that, during a pump shutdown caused by a power outage, the cooling water flow rate exhibited a rapid decrease, reaching fluctuations close to zero, accompanied by the occurrence of a countercurrent phenomenon.…”

Section: Introductionmentioning

confidence: 99%

Pressure Transient Analysis on the Condenser of the HPR1000 Nuclear Power Unit

Lu,

Yang,

Zhang

2024

Energies

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The transient characteristics of pressure in the condenser under fault conditions have a crucial impact on the safe operation of the entire nuclear power plant. In order to ascertain whether the condenser pressure of a HPR1000 nuclear power unit meets the requirements of the steam generator, this paper establishes a mathematical model of the condenser, along with the connected steam turbine bypass steam system and circulating water system, based on Apros. The accuracy of the simulation model is verified by comparing the coasting curve of the circulating water pump with the flow change curve under the pump-tripping condition in Apros. Under the initial CCR condition and the half-side operating condition of the condenser, simulation analyses were conducted for two transient sequences involving the loss of normal external power and the simultaneous tripping of two circulating water pumps. The corresponding changes of pressure in the condenser under the transient sequence were obtained. The study reveals that, under different initial conditions and transient sequences, the condenser pressure of the unit can meet the requirements of a 12 s steam discharge to the condenser before the internal pressure of the condenser reaches the “unavailable” set value when the turbine bypass system is under the fault condition. The research findings of this paper can provide reference data for the design, commissioning, and operation of subsequent HPR1000 nuclear power plants.

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“…The back pressure of the turbine varies with the turbine load, the circulating water flow rate, and the temperature, and the heat transfer performance will be degraded during condenser cycling due to fouling formed by impurities and biomass in the circulating water. Some scholars [18][19][20][21][22][23][24] have established dynamic mathematical models of condensers in large power stations and verified the accuracy and generality of the models. For cold-end systems vs. system power, Chuang C-C et al [25], based on the actual operation of the power plant, found that the efficiency of the stage group increases significantly when the back pressure decreases due to the change in ambient temperature.…”

Section: Introductionmentioning

confidence: 99%

Suitable Analysis of Micro-Increased Capacity Model on Cold-End System of Nuclear Power Plant

Xi,

An,

et al. 2023

Energies

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The cold-end system of a nuclear power plant is a key complex node connecting the power generation system with the variable environmental conditions, and its operation, economy, and stability have become the main obstacles to further improving the performance of the first and second circuits. The current research on the interactions between the cold-end system and the thermal cycle of nuclear power mainly adopts the micropower model, while the existing condenser model does not take into account the influence of the turbine exhaust resistance and exhaust flow and other factors on the condenser vacuum change caused by the change in the circulating water flow rate and temperature in determining the optimal vacuum. This ignores the interactions between the equipment and the interconnections between the parameters, which results in the reduction of the model’s accuracy. This paper takes a nuclear power unit as an example, adopts the “constant flow calculation” method to calculate the heat balance of the two-loop thermal system of the nuclear power plant, and constructs an integrated simulation model of the reaction environment variables, the cold-end system, and the thermal cycle. Taking the circulating water temperature and flow rate as variables, the errors of the separate condenser model and the coupled model in circulating water parameter changes were obtained under the condition of satisfying the thermal system operation, and the circulating water temperature and flow rate change ranges applied by the separate condenser model were analyzed in order to reduce the amount of calculations when the unit power error was 1%. The results show that the circulating water temperature is 4 °C, the applicable range of the circulating water flow rate is 42 m3/s to the rated flow rate, the applicable range of the circulating water temperature is 20 °C, the applicable range of the circulating water flow rate is 32.12 m3/s to the rated flow rate, the applicable range of the circulating water temperature is 26 °C, the applicable range of the circulating water flow rate is 38.63 m3/s to the rated flow rate, the applicable range of the circulating water temperature is 30 °C, and the applicable range of the circulating water flow rate is 45 m3/s to the rated flow rate. At a circulating water temperature of 26 °C, the applicable range of the circulating water flow is between 38.63 m3/s and the rated flow; at a circulating water temperature of 30 °C, the applicable range of the circulating water flow is between 45.64 m3/s and the rated flow.

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Numerical analysis of transient pressure variation in the condenser of a nuclear power station

Cited by 8 publications

References 4 publications

Optimal design of a nuclear power plant condenser control system based on multi-objective optimization algorithm

Optimal design of a nuclear power plant condenser control system based on multi-objective optimization algorithm

Pressure Transient Analysis on the Condenser of the HPR1000 Nuclear Power Unit

Suitable Analysis of Micro-Increased Capacity Model on Cold-End System of Nuclear Power Plant

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