Simulation Study and Parameter Evaluation on Water Level Control System of Steam Generator in Nuclear Power Plant
Chunyu Bi, Pengfei Liu, Xinli Song, Guoyang Wu, Zhida Su
Available Online June 2017.
- https://doi.org/10.2991/caai-17.2017.8How to use a DOI?
- nuclear power plant; SG water level control system; simulation; Nichols curve; parameter evaluation
- Based on a CPR1000 nuclear power plant simulation platform which is developed by Shanghai Jiao Tong University, simulation study and parameter evaluation on the water level control system of Steam Generator have been done in this paper. The response of the SG water level control system is validated by comparing with the design document of SG control system, which is simulated by CATIA2 Code. And then, the controller parameters of SG system are evaluated by Nichols chart and simulation platform. The simulation results show that this simulation platform has a good accordance with the CATIA2 and it can be used in the control system design of nuclear power plant.
- Open Access
- This is an open access article distributed under the CC BY-NC license.
Cite this article
TY - CONF AU - Chunyu Bi AU - Pengfei Liu AU - Xinli Song AU - Guoyang Wu AU - Zhida Su PY - 2017/06 DA - 2017/06 TI - Simulation Study and Parameter Evaluation on Water Level Control System of Steam Generator in Nuclear Power Plant BT - 2017 2nd International Conference on Control, Automation and Artificial Intelligence (CAAI 2017) PB - Atlantis Press SP - 38 EP - 41 SN - 1951-6851 UR - https://doi.org/10.2991/caai-17.2017.8 DO - https://doi.org/10.2991/caai-17.2017.8 ID - Bi2017/06 ER -