scholarly journals Development of AI-Based Simulation System for Man-Machine System Behavior in Accidental Situations of Nuclear Power Plant

1996 ◽  
Vol 33 (2) ◽  
pp. 110-118 ◽  
Author(s):  
Kazuo YOSHIDA ◽  
Masao YOKOBAYASHI ◽  
Fumiya TANABE ◽  
Katumi KAWASE
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Simulation System ◽  
System Behavior ◽  
Machine System

Development and Verification of Severe Accident Simulation Capability for a NPP Simulator

2013 ◽  
Author(s):  
Zhifei Yang ◽  
Xiaofei Xie ◽  
Xing Chen ◽  
Shishun Zhang ◽  
Yehong Liao ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Simulation System ◽  
Severe Accident ◽  
Normal Operation ◽  
Feed Water ◽  
Accident Simulation ◽  
Accident Conditions ◽  
Relap5 Code

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.

Design and Development of Refueling Machine Operation Simulation System in Nuclear Power Plant

2013 ◽  
Vol 373-375 ◽  
pp. 1703-1709
Author(s):  
Jin Jin Xu ◽  
Zhong Wen ◽  
Kai Feng Zhang ◽  
Zheng Gang Guan ◽  
Chen Ye
Keyword(s):  
Virtual Reality ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
3D Modeling ◽  
Nuclear Power ◽  
Failure Modes ◽  
Touch Screen ◽  
Simulation System ◽  
Virtual Reality Technology ◽  
Control Console

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.

A Study on Evaluation Method About Human-Machine System Interface for Nuclear Power Plant

2010 ◽  
Author(s):  
Yongbin Sun ◽  
Pengfei Gu ◽  
Guojin Jiang
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Cognitive Processes ◽  
Nuclear Power ◽  
Human Error ◽  
Evaluation Method ◽  
Control Room ◽  
Machine System ◽  
Room Design ◽  
Operation Control

Now the new control technology has been used in industry including the main control room design of nuclear power plant (NPP). Although We have designed the computerized human-machine system interface (HSI) in Ling Ao Phase II NPP, the old evaluation method about HSI can not be used for the new one. Based on this experience together with reference to the other published information such as NUREG-0700 Rev.2, this study have developed an evaluation method based on a model of human cognitive processes in order to provide the viewpoint of the evaluation on the operability of interface. The method describes systematically the human error categories and evaluation items for HSI. And the method has been evaluated using the evaluation of experimental results obtained by a simulator equipped with computers and touch operation control panels.

scholarly journals Collaborative Emergency Operation of Man-Machine System in Nuclear Power Plant

1998 ◽  
Vol 31 (26) ◽  
pp. 401-406
Author(s):  
Yuji Niwa ◽  
Masahiro Terabe ◽  
Takashi Washio
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Emergency Operation ◽  
Machine System
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