The MSIV Closure Direct Scram Transient Analysis of Lungmen ABWR Using TRACE/PARCS

2012 ◽  
Vol 608-609 ◽  
pp. 844-847
Author(s):  
Jong Rong Wang ◽  
Hao Tzu Lin ◽  
Hsiung Chih Chen ◽  
Chun Kuan Shih
Keyword(s):  
Control System ◽  
Nuclear Power ◽  
Reactor Core ◽  
Pressure Control ◽  
Recirculation Flow ◽  
Vessel Reactor ◽  
Pressure Control System ◽  
Transient Data ◽  
Flow Control System ◽  
Main Steam

This study consists of two steps. The first step is the development of a TRACE (TRAC/RELAP Advanced Computational Engine)/PARCS(Purdue Advanced Reactor Core Simulator) model of Lungmen nuclear power plant (NPP) which includes the vessel, reactor internal pumps (RIPs), main steam lines, and important control systems (such as the feedwater control system, steam bypass & pressure control system, and recirculation flow control system), etc.. Key parameters were identified to refine the TRACE/PARCS model further in the frame of a steady state analysis. The second step is the performance of Lungmen NPP TRACE/PARCS model transient analyses. The MSIV closure direct scram (MSIVCD, MSIV = Main Steamline Isolation Valve) transient data of Final Safety Analysis Report (FSAR) is used to verify the Lungmen NPP TRACE/PARCS model. The trends of TRACE/PARCS analysis results are consistent with the FSAR data. It indicates that there is a respectable accuracy in the Lungmen NPP TRACE/PARCS model.

The Load Rejection Transient Analysis of Chinshan NPP (BWR/4) Using TRACE/PARCS

2014 ◽  
Author(s):  
Jhih-Jhong Huang ◽  
Hsiung-Chih Chen ◽  
Jong-Rong Wang ◽  
Lih-Yih Liao ◽  
Chunkuan Shih ◽  
...  
Keyword(s):  
Control System ◽  
Nuclear Power ◽  
Thermal Power ◽  
Reactor Core ◽  
Second Step ◽  
System Response ◽  
Recirculation Flow ◽  
Fuel Assemblies ◽  
Flow Control System ◽  
Main Steam

Chinshan Nuclear Power Plant (NPP) is the first boiling water reactor (BWR) NPP in Taiwan. It has two units of BWR/4 reactor made by GE Company and each rated thermal power was 1775 MW without power uprate (now its rated thermal power is 1805 MW after power uprate). This research focuses on the development of the Chinshan NPP TRACE (TRAC/RELAP Advanced Computational Engine)/PARCS (Purdue Advanced Reactor Core Simulator) model. The model is done in two steps: The first step is the development of a TRACES/PARCS model of Chinshan NPP which includes the vessel, fuel assemblies, the main steam lines and important control systems (such as the feedwater control system, recirculation flow control system, etc.). Key parameters (such as power, feedwater flow rate, reactor dome temperature, etc.) were identified to refine the model further in the frame of a steady state analysis. The second step is development of TRACE/PARCS model for the load rejection transient. In order to check the system response of the Chinshan NPP TRACE/PARCS model, this study uses the load rejection transient results of startup tests to benchmark the analysis results of Chinshan NPP TRACE/PARCS model. The trends of TRACE/PARCS analysis results were consistent with the startup test data. It indicates that there is a respectable accuracy in the Chinshan NPP TRACE/PARCS model for the load rejection transient.

Study of the Characteristic Response of Pressure Control System in Order to Obtain the Design Parameters of the New Control System MARK VI Turbine in Cofrentes Nuclear Power Plant

2010 ◽  
Author(s):  
Laura Bucho´ ◽  
Mari´a Jose´ Palomo ◽  
Juan Ignacio Vaquer ◽  
Bele´n Lo´pez ◽  
Gregorio Rui´z ◽  
...  
Keyword(s):  
Control System ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Technical Specification ◽  
Pressure Control ◽  
Design Parameters ◽  
Sensor Signal ◽  
Bode Plot ◽  
Pressure Control System

This paper presents the results obtained from the IBE-CNC/DAQ-090827 project, conducted by the company “Titania Servicios Tecnolo´gicos, S.L.” in collaboration with the “Instituto de Seguridad Industrial, Radiofi´sica y Medioambiental” (ISIRYM), in the “Universidad Polite´cnica de Valencia”, for the company “Iberdrola Generacio´n S.A”. The objective is the acquisition of the pressure sensor signal and the measurement at points C85 and N32 from the cabin of the Turbine Control System in Cofrentes Nuclear Power Plant. With the study of previous data, one can obtain the Bode plot of the crossed signals as requested in the technical specification IM 0191 I. Frequency response (i.e. how the system varies its gain and offset depending on the frequency) defines the dynamics.

RETRAN Application of Turbine Trip and Load Rejection of Startup Test Analysis for Lungmen ABWR

2009 ◽  
Author(s):  
Chen-Lin Li ◽  
Chiung-Wen Tsai ◽  
Chunkuan Shih ◽  
Jong-Rong Wang ◽  
Su-Chin Chung
Keyword(s):  
Control System ◽  
Water Level ◽  
Control Systems ◽  
Nuclear Power ◽  
Pressure Control ◽  
Reactor Power ◽  
Level Control ◽  
Bypass Flow ◽  
Control Rod ◽  
Recirculation Flow

This study used RETRAN program to analyze the turbine trip and load rejection transients of Taiwan Power Company Lungmen Nuclear Power Plant’s startup test at 100% power and 100% core flow operating condition. This model includes thermal flow control volumes and junctions, control systems, thermal hydraulic models, safety systems, and 1D kinetics model. In Lungmen RETRAN model, four steam lines are simulated as one line. There are four simulated control systems: pressure control system, water level control system, feedwater control system, and speed control system for reactor internal pumps. The turbine trip event, at above 40% power, triggers the fast open of the bypass valves. Upon the turbine trip, the turbine stop valves close. To minimize steam bypassed to the main condenser, recirculation flow is automatically runback and a SCRRI (selected control rod run in) is initiated to reduce the reactor power. The load rejection event causes the fast opening of the bypass valves. Steam bypass will sufficiently control the pressure, because of their 110% bypass capacity. A SCRRI and RIP runback are also initiated to reduce the reactor power. This study also investigated the sensitivity analysis of turbine bypass flow, runback rate of RIPS and SCRRI to observe how they affect fuel surface heat flux, neutron flux and water level, etc. The results show that turbine bypass flow has larger impacts on dome pressure than RIPS runback rate and SCRRI. This study also indicates that test criteria in turbine trip and load rejection transients are met and Lungmen RETRAN model is performing well and applicable for Lungmen startup test predictions and analyses.

Study on the CFBB Main Steam Pressure Control System Based on ADRC Technology

2013 ◽  
Vol 291-294 ◽  
pp. 2470-2473 ◽  
Author(s):  
Jia Liang Zheng ◽  
Li Xiang Zhang ◽  
Pei Hua Zhang
Keyword(s):  
Control System ◽  
Pid Control ◽  
Combustion Process ◽  
Pressure Control ◽  
Steam Pressure ◽  
Operating Conditions ◽  
Excellent Performance ◽  
Adjustment Time ◽  
Pressure Control System ◽  
Main Steam

The combustion process of CFBB is a system with time-varying, nonlinear, large inertia and time delay. Therefore the control effects of traditional PID control system in the CFBB plant are not satisfactory , especially the overshoot of the main steam pressure control system is very big, and the adjustment time is too long. To improve the performance of the main steam pressure control system, ADRC technology was used . The disturbed signal was added in the different operating conditions, the testing results indicated that the ADRC main steam pressure control system had more excellent performance than the convention PID method.

scholarly journals Parametric analysis of pressure control system for Lungmen nuclear power plant

2012 ◽  
Vol 14 ◽  
pp. 1082-1086
Author(s):  
Chiung-Wen Tsai ◽  
Chunkuan Shih ◽  
Jong-Rong Wang ◽  
Hao-Tzu Lin ◽  
Su-Chin Cheng ◽  
...  
Keyword(s):  
Control System ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Parametric Analysis ◽  
Nuclear Power ◽  
Pressure Control ◽  
Pressure Control System

Study on Fuzzy Immune PID Controller for Main Steam Pressure Control System in Marine Steam Power Plant

2014 ◽  
Vol 686 ◽  
pp. 89-94
Author(s):  
Peng Wang ◽  
Meng Hao ◽  
Qing Zhou Ji
Keyword(s):  
Control System ◽  
Power Plant ◽  
Pid Controller ◽  
Fuzzy Controller ◽  
Pressure Control ◽  
Steam Pressure ◽  
Steam Power ◽  
Steam Power Plant ◽  
Pressure Control System ◽  
Main Steam

The main steam pressure control system in marine steam power plant has the characteristics of time-varying, nonlinear and strong coupling. In order to get satisfactory control effect, we propose a fuzzy immune PID controller with which we can make comprehensive utilization of advantages of artificial immune, PID and fuzzy controller. We build up mathematical model of main steam pressure control system, carry out simulation and comparison. The results prove that fuzzy immune PID controller can significantly reduce the overshoot and settling time of main steam pressure. It is more effective in main steam pressure control system than PID controller.

Research on Pressurizer Pressure Control System of 900MW Pressurized Water Reactor Nuclear Power Plant

2013 ◽  
Vol 718-720 ◽  
pp. 1215-1220
Author(s):  
Guo Duo Zhang ◽  
Xu Hong Yang ◽  
Si Yu Qiao ◽  
Yu Jun Wu
Keyword(s):  
Control System ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Control Method ◽  
Pressure Control ◽  
Sharp Change ◽  
Control Technology ◽  
Pressurized Water ◽  
Pressure Control System

It is of vital importance for the pressurizer to maintain the pressure of primary coolant because the sharp change of coolant pressure has a direct impact on the security of reactor. The study of pressurizers pressure control method is highly important and meaningful. This paper presents the researching and designing on pressure control system of a pressurizer implemented in a nuclear power plant. Both the present situation of the nuclear power and some relevant background have been briefly introduced. Proceeding on the records of simulation, we succeed in establishing the applied modeling of pressurizer and further propose the PID control technology working as control algorithm. The best set of controller parameters are chosen through comparing the results including regulation time, overshoot suppression and stability. On the base of such control method, we attempt to add neural network control technology to achieve further improvement, which turns out available and satisfying.

Sign in / Sign up

Export Citation Format

Share Document