ICONE23-1601 ANALYSIS STABILIZATION TECHNIQUE OF NUCLEAR POWER PLANT SIMULATION SYSTEM

Author(s):  
Kenichi Katono ◽  
Yoshihiko Ishii
2012 ◽  
Vol 249 ◽  
pp. 41-48 ◽  
Author(s):  
Chung-Yu Yang ◽  
L.C. Dai ◽  
Thomas K.S. Liang ◽  
B.S. Pei ◽  
C.K. Shih ◽  
...  

1982 ◽  
Vol 104 (3) ◽  
pp. 270-274 ◽  
Author(s):  
S. Thompson

A procedure is presented for designing multivariable controllers for unidentified plant. It is assumed that the open-loop plant is stable and its response to step inputs are basically nonoscillatory. For such plant, no mathematical model is required in order to generate multivariable I, PI, or PID controllers. Method of tuning the controllers are also presented and demonstrated, first on a low order linear distillation column model, and finally on a high order, nonlinear, once-through boiler model typical of the type used in nuclear power plant simulation studies.


Author(s):  
Zhifei Yang ◽  
Xiaofei Xie ◽  
Xing Chen ◽  
Shishun Zhang ◽  
Yehong Liao ◽  
...  

It is reflected in the severe accident in Fukushima Daiichi that the emergency capacity of nuclear power plant needs to be enhanced. A nuclear plant simulator that can model the severe accident is the most effective means to promote this capacity. Until now, there is not a simulator which can model the severe accident in China. In order to enhance the emergency capacity in China, we focus on developing a full scope simulator that can model the severe accident and verify it in this study. The development of severe accident simulation system mainly includes three steps. Firstly, the integral severe accident code MELCOR is transplanted to the simulation platform. Secondly, the interface program must be developed to switch calculating code from RELAP5 code to MELCOR code automatically when meeting the severe accident conditions because the RELAP5 code can only simulate the nuclear power plant normal operation state and design basis accident but the severe accident. So RELAP5 code will be stopped when severe accident conditions happen and the current nuclear power plant state parameters of it should be transported to MELCOR code, and MELCOR code will run. Finally, the CPR1000 nuclear power plant MELCOR model is developed to analyze the nuclear power plant behavior in severe accident. After the three steps, the severe accident simulation system is tested by a scenario that is initiated by the station black out with reactor cooling pump seal leakage, HHSI, LHSI and auxiliary feed water system do not work. The simulation result is verified by qualitative analysis and comparison with the results in severe accident analysis report of the same NPP. More severe accident scenarios initiated by LBLOCA, MBLOCA, SBLOCA, SBO, ATWS, SGTR, MSLB will be tested in the future. The results show that the severe accident simulation system can model the severe accident correctly; it meets the demand of emergency capacity promotion.


Author(s):  
Thomas A. Ulrich ◽  
Roger Lew ◽  
Steffen Werner ◽  
Ronald L. Boring

We demonstrate the development, rationale, and use of a gamified microworld nuclear power plant simulation for engineering psychology research and process control applications. The Rancor microworld was developed to address specific research needs in support of ongoing U.S. nuclear control room modernization efforts. The Rancor microworld serves as a platform for inexpensive cognitive psychology research that would otherwise not be as feasible in typical complex process control research settings. The gamified nuclear power plant simulator is simple enough that untrained, novice participants can quickly learn and control the system. The Rancor microworld is currently configured to support an investigation of attention and situation awareness in nuclear process control is discussed. The Rancor framework is flexible to support rapid modification for addressing research needs related to complex process control.


2013 ◽  
Vol 373-375 ◽  
pp. 1703-1709
Author(s):  
Jin Jin Xu ◽  
Zhong Wen ◽  
Kai Feng Zhang ◽  
Zheng Gang Guan ◽  
Chen Ye

In order to improve the effect of refueling training in nuclear power plant, the simulation system of refueling machine was designed and developed, combining the virtual reality technology with a real control console. The 3D virtual refueling environment of nuclear power plant was established by 3D modeling. Signals from touch screen and console are gathered by PLC and transmitted to PC graphics workstation, control the motion of virtual refueling machine, which realize the refueling operation simulation. The operation in failure modes was also realized in the system through the programming of failure database. The results show that the system runs normally and can simulate refueling operation in normal and abnormal modes, the training of refueling personnel is implemented effectively.


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