Research on Real-Time Simulation of Steam Dump Control System in PWR Nuclear Power Plants

WANG Baosheng; WANG Dongqing; ZHANG Jianmin; QIU Jianwen; WANG Jian

Volume 32 Issue 5

Mar. 2025

Turn off MathJax

Article Contents

Abstract

References

Article Navigation > Nuclear Power Engineering > 2011 > 32(5): 38-44

WANG Baosheng, WANG Dongqing, ZHANG Jianmin, QIU Jianwen, WANG Jian. Research on Real-Time Simulation of Steam Dump Control System in PWR Nuclear Power Plants[J]. Nuclear Power Engineering, 2011, 32(5): 38-44.

Citation:

WANG Baosheng, WANG Dongqing, ZHANG Jianmin, QIU Jianwen, WANG Jian. Research on Real-Time Simulation of Steam Dump Control System in PWR Nuclear Power Plants[J]. Nuclear Power Engineering, 2011, 32(5): 38-44.

Citation:

PDF( 428 KB)

Research on Real-Time Simulation of Steam Dump Control System in PWR Nuclear Power Plants

1. Xi'an Jiaotong University, Xi'an, 710049, China;
2. Beijing Division, China Nuclear Power Technology Research Institute, Beijing, 100086, China

Received Date: 2010-04-29
Available Online: 2025-03-08

Abstract

Abstract

In order to analyze the dynamic response performance of steam dump control system,the real-time simulation model of steam dump control system in NPPs is established.Based on this model,a real-time calculation code is programmed to dynamically simulate the behavior of the control system.The visual and real-time simulation for closed loop condition,such as steady state and transient state,is performed with this code.The agreement between simulation results and the practical response of the control system is reasonable.The real-time property of the model can be verified for the steam dump control system.
- PWR,
- Steam dump control,
- Real-time simulation,
- Visualization

FullText(HTML)

References(0)

References

Relative Articles

[1]	Ye Yaoxin, Zhao Jun, Bao Pengfei, Yu Chao, Jiang Pingting. Acceleration Method and Verification of Theoretical Calculation of Irradiation Supervision for Pressurized Water Reactor[J]. Nuclear Power Engineering, 2024, 45(6): 30-38. doi: 10.13832/j.jnpe.2024.06.0030
[2]	Wang Yue, Yuan Tianrun, Zhuang Yaping, Zhang Jin, Zhou Yuanyuan, Han Xiaoqu. Research on Dynamic Characteristics of PWR Nuclear Power Unit under Variable Power Loads Based on APROS[J]. Nuclear Power Engineering, 2024, 45(1): 210-217. doi: 10.13832/j.jnpe.2024.01.0210
[3]	Chen Jiajie, Liu Xiaojing, Du Sijia, Wang Jiageng, He Hui. Prediction Model for Growth of Chalk River Unidentified Deposit on the Surface of PWR Fuel Cladding[J]. Nuclear Power Engineering, 2023, 44(5): 210-215. doi: 10.13832/j.jnpe.2023.05.0210
[4]	Li Fuhai, Lin Yunliang, Lin Zijian, Lin Genxian, Guo Zifang, Fang Jun, Lin Mingzhang. Research on Calculation of Coolant Radiolysis Products in Operating Conditions during the Shutdown of PWRs[J]. Nuclear Power Engineering, 2023, 44(3): 202-209. doi: 10.13832/j.jnpe.2023.03.0202
[5]	Qin Junwei, Li Yunzhao, Wang Kunpeng, Wu Hongchun, Cao Liangzhi. Three-Dimensional Pin-by-pin Transient Analysis for PWR-Core[J]. Nuclear Power Engineering, 2023, 44(6): 32-38. doi: 10.13832/j.jnpe.2023.06.0032
[6]	Zhang Xianshan, Sun Peiwei, Wei Xinyu. Dynamic Characteristic Analysis of Steam Bypass Exhaust System of Steam Turbine[J]. Nuclear Power Engineering, 2021, 42(S2): 25-28. doi: 10.13832/j.jnpe.2021.S2.0025
[7]	Zhang Jie, Zhou Jianqiu, Xu Xinwei, Liu Quanchang. Research and Application of 3D Visual Reinforcement System for Nuclear Power Containment Shell[J]. Nuclear Power Engineering, 2021, 42(3): 103-108. doi: 10.13832/j.jnpe.2021.03.0103
[8]	Cui Huaiming, Zhou Jinman. Research on Overall Design of Operation Mode in PWR Nuclear Power Plants[J]. Nuclear Power Engineering, 2020, 41(4): 203-207.
[9]	Xu Yanfeng, Zhang Pengfei. Research on Calculations of Radioactive Source Terms for PWR Nuclear Power Plants[J]. Nuclear Power Engineering, 2019, 40(1): 116-119. doi: 10.13832/j.jnpe.2019.01.0116
[10]	Yuan Guanghui, Liu Dong, Yu Hongxing, Hao Jiangtao, Qiang Shenglong, Liu Ying, Cao Guohai. Research of Visual Conversion Technology for Reactor Core Monte Carlo Model Based on CSG[J]. Nuclear Power Engineering, 2019, 40(3): 180-184. doi: 10.13832/j.jnpe.2019.03.0180
[11]	Ru Jun, Xiao Zhong, Zhu Fawen, Zhang Lin, Qin Mian, Liu Yanghua. Analysis of Measures for Safe Operation of PWR Fuel Assemblies[J]. Nuclear Power Engineering, 2017, 38(6): 175-179. doi: 10.13832/j.jnpe.2017.06.0175
[12]	Duan Xinhui, Wang Bingshu, JIang Ping. Application of Nonlinear Iteration Method in Reactor Real-Time Simulation[J]. Nuclear Power Engineering, 2017, 38(S2): 182-187. doi: 10.13832/j.jnpe.2017.S2.0182
[13]	Zhang Junyi, Yan Xiao, Xu Jianjun, Huang Yanping. Phenomenological Investigation of Gas Bubble Behavior in the Vicinity of Mixing Vane of Spacer Grid[J]. Nuclear Power Engineering, 2016, 37(6): 164-167. doi: 10.13832/j.jnpe.2016.06.0164
[14]	HE Peifeng, WANG Qingtian, ZHANG Yi, MU Dianpeng, LI Yan, LI Ning. Analysis and Control of Welding Deformation of Nuclear Power Reactor Plant CRDM Anti-Seismic Ring[J]. Nuclear Power Engineering, 2013, 34(S1): 109-111,119.
[15]	MA Jian, HUANG Yanping, HUANG Jun. Visual Investigations of Temperature on Outer Wall of Narrow Rectangular Channel with Longitudinal Vortex[J]. Nuclear Power Engineering, 2012, 33(1): 46-50.
[16]	WEN Qinglong, CHEN Jun, LU Donghua, ZHAO Hua. Visual Experimental Study on Bubble Behavior on Inclined Downward Facing Surfaces[J]. Nuclear Power Engineering, 2012, 33(3): 51-55.
[17]	XIAO Hongguang, ZHU Bo, ZHANG Fan. Simulation on In-Containment Source Term and Virtual Accident Scene of Large-Break LOCA[J]. Nuclear Power Engineering, 2011, 32(3): 25-28,42.
[18]	XIE Zhangji, ZHU Bo, CHEN Yuqing, LI Shiting. Visualization Research of 3D Radiation Field Based on Delaunay Triangulation[J]. Nuclear Power Engineering, 2011, 32(5): 128-132.
[19]	MA Jian, HUANG Yanping, HUANG Jun. Visual Experimental Investigations on Single-Phase Flow in Narrow Rectangular Channel with Longitudinal Vortex[J]. Nuclear Power Engineering, 2011, 32(1): 85-88.
[20]	DING Xiaochuan, LU Haijin, ZHAO Qiang. An Arithmetic for Core Physics Real-time Simulation Based on ADI[J]. Nuclear Power Engineering, 2011, 32(3): 130-133.