A design of human–machine interface for the two-modular high-temperature gas-cooled reactor nuclear power plant

2014 ◽  
Vol 77 ◽  
pp. 336-343 ◽  
Author(s):  
Qianqian Jia ◽  
Xiaojin Huang ◽  
Liangju Zhang
Keyword(s):  
High Temperature ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Human Machine Interface ◽  
Machine Interface ◽  
High Temperature Gas

Verification of Alarm Displays for the Nuclear Power Plant With Two Modular High-Temperature Gas-Cooled Reactors

2018 ◽  
Author(s):  
Jia Qianqian ◽  
Guo Chao ◽  
Li Jianghai ◽  
Qu Ronghong
Keyword(s):  
High Temperature ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Modular Design ◽  
Early Stage ◽  
Integrated System ◽  
Alarm System ◽  
Control Room ◽  
High Temperature Gas

The nuclear power plant with two modular high-temperature gas-cooled reactors (HTR-PM) is under construction now. The control room of HTR-PM is designed. This paper introduces the alarm displays in the control room, and describes some verification and validation (V&V) activities of the alarm system, especially verification for some new human factor issues of the alarm system in the two modular design. In HTR-PM, besides the regular V&V similar to other NPPs, the interference effect of the alarm rings of the two reactor modules at the same time, and the potential discomfort of the two reactor operators after shift between them are focused. Verifications at early stage of the two issues are carried on the verification platform of the control room before the integrated system validation (ISV), and all the human machine interfaces (HMIs) in the control room, including the alarm system are validated in ISV. The test results on the verification platform show that the alarm displays and rings can support the operators understand the alarm information without confusion of the two reactors, and the shift between the two reactor operators have no adverse impact on operation. The results in ISV also show that the alarm system can support the operators well.

Assessment of human–machine interface design for a Chinese nuclear power plant

2005 ◽  
Vol 87 (1) ◽  
pp. 37-44 ◽  
Author(s):  
Chen Xiaoming ◽  
Zhou Zhiwei ◽  
Gao Zuying ◽  
Wu Wei ◽  
Takashi Nakagawa ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Interface Design ◽  
Nuclear Power ◽  
Human Machine Interface ◽  
Machine Interface

Digital Human-Machine Interface Design for Marine Nuclear Power Plant Based on Task-Oriented

2017 ◽  
Author(s):  
Zhi-tong Liu ◽  
Shao-ming Wang ◽  
Long-fei Zhang ◽  
Guang Yang ◽  
Meng Lv ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Digital Control ◽  
Nuclear Power ◽  
Human Machine Interface ◽  
Control Room ◽  
Large Display ◽  
Machine Interface ◽  
Task Oriented ◽  
And Control

A design of human machine interface (HMI) has been developed to ensure the safety and availability of marine nuclear power plant (NPP) in China. The staffing arrangement and HMIs are different from current nuclear power plants. One control room is used to monitor and control the reactor, the secondary loop, and the electric system. Considering the digital control room style, the elements of the HMIs in the control room are the large display panels and control consoles. Considering the digital control room style, the elements of the HMIs in the control room are the large display panels and control consoles. Information accuracy and control efficacy are thought as the ultimate goal. It has extremely high safety by hardware control on the control panel. Display device refers to the part designs of NPP one. Eventually it can provide centrally the working condition of the device and system, the operating parameters of key equipment, accident. Dynamic and static displays are combined to reflect real-time condition of the system conveniently, accurately and reliably. The necessary safety operations and displays are set on the safety console of each reactor independently. The large display panels are designed as an overview of the whole marine plant, which consist of large screen displays, mimic displays and alarm tiles. This paper points out that what the main issues is to be dealt with in the computerized HMI design process. A task-oriented HMI design principle is used to the interfaces of marine reactors starting up.

A Study About Human Workload Forecasting Method of Nuclear Power Plant

2010 ◽  
Author(s):  
Guojin Jiang ◽  
Pengfei Gu ◽  
Yongbin Sun
Keyword(s):  
Performance Evaluation ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Team Performance ◽  
Nuclear Power ◽  
Individual Performance ◽  
Human Machine Interface ◽  
Team Work ◽  
Operator Performance ◽  
Machine Interface

In the past, the human machine interface is not computerized and the analysis tools are lack. So that most of previous researches of operator performance focused on the performance of individual operator rather than on the team performance. The relationships between team performance and individual performance are very close, but the team performance is not exactly equal to the sum of individual performance. The complexity of team performance evaluation is much higher than that of individual performance evaluation. Along with the development of new technology, especially the computerized technology, such as eye tracking tool and video recorder, team performance could be observed and measured. In NPP (Nuclear Power Plant), the operator performance of team work is closed to the safety of the whole plant. So the operators needed to be paid high attention to team performance. In order to improve the operator performance (including individual and team performance) base on the computerized human machine interface, this study bends to develop a real-time warning model for assessing team performance through the mental workload and human reliability evaluation. According to the analysis result, it could be as reference to modify the design about human machine interface in order to increase system safety and team performance of NPP.

A Study on Human Reliability About Human Machine Interface in Accident Situation of Nuclear Power Plant

2010 ◽  
Author(s):  
Pengfei Gu ◽  
Zhifang Wang ◽  
Jianbo Zhang
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Human Performance ◽  
Human Machine Interface ◽  
Team Work ◽  
Control Room ◽  
Human Reliability ◽  
Human Reliability Analysis ◽  
Machine Interface

Recently Human Reliability Analysis (HRA) is becoming more important to the safety of nuclear power plant (NPP). As the reliability of the NPP equipments have been increased more higher, HRA should be developed in order to guarantee the better safety of NPP. By the collection of human performance about operators in main control room of NPP, especially in accident situation, it is very important to enhance the human reliability. This paper chooses Loss of Coolant Accident (LOCA) and Steam Generator Tube Rupture (SGTR) as the initiating events, and base on this, some loss of other equipment or system have been added. Then the process that the operators deal with the accidents has been recorded in the accident situation in order to get reasonable human performance data. After we analyzed all of these video by some tools such as eye tracking tool, some items have been found which are very important to the human reliability such as training level, operation task, human-machine interface, surrounding, team work, etc. According to the analysis of the human performance result, we have evaluated the computerized human machine interface. As a result, it also could be benefit to improve the design of NPP, specially the design of main control room.

Thermal Efficiency Optimization of a Modular High Temperature Gas-Cooled Reactor Plant by Extraction Steam Distribution

2020 ◽  
Author(s):  
Di Jiang ◽  
Zhe Dong
Keyword(s):  
High Temperature ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Thermal Efficiency ◽  
Nuclear Power ◽  
Normal Operation ◽  
Efficiency Optimization ◽  
Load Following ◽  
Fluid Network ◽  
High Temperature Gas

Abstract Modular high temperature gas-cooled reactor (MHTGR) is a small modular reactor (SMR) with inherent safety, which is suitable for load following to improve economic competitiveness. The heat regenerative system for MHTGR nuclear power plant, is crucial for the improvement of thermal efficiency. Traditionally, the enthalpy drop distribution method (EDM) is used to study the relationships between thermal efficiency and distribution of extraction steam. However, this strategy is mainly used for off-line design of steam turbine under rated conditions. For load following operation, it is hard to guarantee the extraction steam distribution of EDM due to the highly nonlinear “flowrate-pressure-temperature” coupling of the fluid network. Thus, in this paper, the thermal efficiency is derived analytically based on the steady state model of fluid network. Then the thermal efficiency optimization is cast into a nonlinear programming problem, in which physical constraints can be considered explicitly. The proposed method for extraction steam distribution is of significance for improving the thermal efficiency of normal operation of nuclear power plant.

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