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.

Applying Engineering Simulator to Verification and Validation of Digital I&C in Nuclear Power Plant

2009 ◽  
Author(s):  
Meng Lin ◽  
Zongwei Yang ◽  
Dong Hou ◽  
Pengfei Liu
Keyword(s):  
Control System ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Water Level ◽  
Control Systems ◽  
Nuclear Power ◽  
Verification And Validation ◽  
Level Control ◽  
Actuation System ◽  
Reactor Protection System

In China, more and more Nuclear Power Plant (NPP) will be constructed in the near future years, and Main Control Room (MCR) will introduce digital Instrumentation and Controls systems (I&C) technique. I&C system of nuclear power plant consists of Control Systems, Reactor Protection System and Engineered Safety Feature (ESF) Actuation System. For example, I&C system of LinAo Phase II NPP has adopted SIEMENS TXP and TXS I&C, which is being constructed in Guangdong province, China. In this engineering project, Chinese engineers are responsible for all the configuration of actual analog and logic diagram. Before the phase of real plant testing on the reactor, engineers want to make sure that configuration is right and control functions can be accomplished, so primary Verification and Validation (V&V) of I&C works were done. One way is checking the diagram configuration one by one according to the original design. There are two main disadvantages. One is diagram is so complex that workload is very large and engineers will make mistake. Another is even engineers have read every logic, but they still cannot know the final results and function of a complex control system. So another effective V&V way is applying NPP engineering simulator to do virtual test. According to LinAo Phase II NPP design, we develop one simulator to construct a virtual NPP model as a basis, which can provide plant operation parameters and can also accept control signal from I&C, then give response to it. Through this way, we don’t need to know the exact diagram, and just observe input and output of I&C to make sure that the final results is right and functions have been accomplished. In this way, it is need to transfer signals between simulator and I&C. For keeping the original software and hardware structures of SIEMENS Distributed Control System (DCS), we use one set of data acquisition (DAQ) equipments to build a connection between the engineering simulator (software) and SIEMENS DCS I/O cabinet (hardware), and the interface is standard 4–20mA direct current and 0–48V direct voltage. This way is convenient for expansion to other digital I&C V&V. After these two V&V works, we can then build the confidence of digital I&C control function. As an application research, we mainly focus on V&V of digitalized control systems and selected several Reactor Control (RRC) systems as examples, including pressurizer pressure and water level control, steam generator water level control. In this paper, we will introduce the way of applying engineering simulator to do V&V works, the structure of our simulator, the function of different block, and primary V&V results. Moreover, we will have ideas on the future application of this methodology to V&V of Reactor Protection System and ESF Actuation System.

Computerized Water Level Control System for System Generator of Qinshan Nuclear Power Plant

1997 ◽  
Vol 30 (17) ◽  
pp. 155-160
Author(s):  
Wen-peng Lang ◽  
M. Tahir Khaleeq ◽  
David Guosen He ◽  
Weiqing Zhao
Keyword(s):  
Control System ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Water Level ◽  
Nuclear Power ◽  
Level Control ◽  
System Generator ◽  
Level Control System

scholarly journals Power Level Control of Nuclear Power Plant Based on Asymptotical State Observer under Neutron Sensor Fault

2021 ◽  
Vol 2021 ◽  
pp. 1-8
Author(s):  
Liming Zhang ◽  
Hongyun Xie ◽  
Qizhi Duan ◽  
Chao Lu ◽  
Jixue Li ◽  
...  
Keyword(s):  
Control System ◽  
Power Control ◽  
Control Systems ◽  
Nuclear Power ◽  
Power Plants ◽  
Power Level ◽  
Level Control ◽  
Power Control System ◽  
Neutron Sensors ◽  
And Control

Power level control is one of the critical functions in the instrument and control system of nuclear power plants (NPPs). In most power level control systems of NPPs, the power level or average neutron flux in reactor cores provided by out-of-core neutron sensors are usually measured as feedback of power control systems, while, as critical measuring devices, there is a risk of damage to out-of-core neutron sensors. For improving the operation reliability of NPPs under the neutron sensors’ failure, a power control system based on power observer is developed in this work. The simulation based on NPP simulator shows the power control system based on the observer is effective when neutron sensors fail.

scholarly journals Active Fault Tolerant Control System for the Measurement Circuit in a Drum Boiler Feed-Water Control System

2018 ◽  
Vol 51 (1-2) ◽  
pp. 4-15 ◽  
Author(s):  
Mariusz Pawlak
Keyword(s):  
Control System ◽  
Water Level ◽  
Control Systems ◽  
Power Unit ◽  
Fault Tolerant ◽  
Diagnostic System ◽  
Fault Tolerant Control ◽  
Level Control ◽  
Level Control System ◽  
Boiler Drum

This paper presents a water-level control system in a drum boiler. The system was equipped with a fault tolerant control–type diagnostic system. The paper presents the results of tests conducted on the fault tolerant control system implemented in the water-level control system in a boiler drum. The diagnostics of the measurement circuits was carried out online. To that end, the appropriate partial models were developed and tested. This allowed for the application of analytical redundancy for the measurement circuits. The paper also identifies the influence of diagnostics and fault tolerance on the values of reliability indices and operating safety of a power unit. Fault tolerant control systems increase the safety of a power unit operation, and the studies described in the paper directly contribute to them. These kinds of systems have not been used so far in power unit automation. Site tests confirmed the validity of the acquired concept for the diagnostic system. Fault tolerant control systems have not been commonly applied in power engineering yet. Studies of the water-level control system in a steam drum using the fault tolerant control system for the measurement circuits as presented in the paper are original ideas, providing a new solution. All control systems made for the study fulfil their role in a satisfactory way, which results in a minor deviation in the water-level adjustment in the boiler drum. The tests confirmed the efficiency of the fault detection algorithm. The created models of the water level and flows proved to be successful. Under a no-fault condition of the facility, there were no errors in the diagnoses and the values of all residua were below the detection thresholds. This was achieved despite a high value of measurement noises. The residua helped detect minor faults.

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.

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