Improvement and optimization of master/bypass valve switching process for steam generator level control of nuclear power plant

被引：0

作者：

Chen, Yong-Wei ^{[1
]}

Fu, Jing-Qiang ^{[1
]}

Qiu, He-Wen ^{[1
]}

Zhang, Li-Guo ^{[1
]}

You, Dai-Lun ^{[1
]}

机构：

[1] China Nuclear Power Co., Ltd., Shenzhen

来源：

Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2015年 / 49卷 / 03期

关键词：

CPR1000; units; Master/bypass valve; PID regulator; Steam generator; Water level control;

D O I：

10.7538/yzk.2015.49.03.0523

中图分类号：

学科分类号：

摘要：

According to the statistics of domestic nuclear power plant CPR1000 units, the common failure modes in the steam generator level control about the master/bypass valve switching process were described. The main modes include that the master/bypass valve switching threshold owes excellent, the master/bypass valve frequently switches and the master valve opens too late. And then a solution was raised about how to improve the master/bypass valve switching process, including switching point optimization, disturbance value control and difference control. This solution is performed in the project site and is verified feasible and effective. ©, 2015, Atomic Energy Press. All right reserved.

引用

页码：523 / 528

页数：5

共 8 条

[1]

Qian H., Ye J., Qian F., Digitization and simulation realization of full range control system for steam generator water level, Nuclear Power Engineering, 31, 2, pp. 58-62, (2010)

[2]

Huang X., Wang Q., Wang R., Prediction of the performance of flooded refrigerant evaporators based on a distributed parameter model, Journal of Shanghai Jiaotong University, 38, 7, pp. 1164-1169, (2004)

[3]

Zhang Y., Guo L., Cai M., Study on PID control system based on fuzzy self-adaptive parameter-adjustive technique of once-through steam generator, Nuclear Power Engineering, 29, 4, pp. 93-96, (2008)

[4]

Fu M., Shi X., Chen D., Study on the control system of a once-through steam generator, Chinese Journal of Nuclear Science and Engineering, 22, 2, pp. 108-112, (2002)

[5]

Ma S., Trip analysis and online diagnosis regulation for loosing water level control of the PWR steam generator, Chinese Journal of Nuclear Science and Engineering, 29, 4, pp. 328-340, (2009)

[6]

Li F., Zhang D., Wang S., PID control for nuclear generator water level based on genetic algorithm, Atomic Energy Science and Technology, 42, 1, pp. 137-141, (2008)

[7]

Gan J., Study on the improvement of steam generator, Chinese Journal of Nuclear Science and Engineering, 15, 3, pp. 193-198, (1995)

[8]

Bai L., Lin G., Zhang H., Steady state modeling of loop heat pipes and operating characteristics analysis, Journal of Beijing University of Aeronautics and Astronautics, 32, 8, pp. 894-898, (2006)

← 1 →