• Nuclear Engineering and Technology
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• v.32 no.1
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• pp.88-98
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• 2000

More than half of all incidents in large complex technological systems, particularly in nuclear power or aviation industries, were attributable in some way to human erroneous actions. These incidents were largely due to the human engineering deficiencies of man-machine interface (MMI). In nuclear industry, advanced computer-based MMI designs are emerging as part of new reactor designs. The impact of advanced MMI technology on the operator performance, and as a result, on plant safety should be thoroughly evaluated before such technology is actually adopted in nuclear power plants. This paper discusses the applicability of human reliability analysis (HRA) to support the design review process. Both the first-generation and the second-generation HRA methods are considered focusing on a couple of promising HRA methods, i.e., ATHEANA and CREAM, with the potential to assist the design review process.

• Journal of the Ergonomics Society of Korea
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• v.22 no.1
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• pp.31-42
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• 2003

This study describes a modification of the technique for human error analysis in nuclear power plants (NPPs) which adopts advanced Man-Machine Interface (MMI) features based on computerized working environment, such as LCOs. Flat Panels. Large Wall Board, and computerized procedures. Firstly, the state of the art on human error analysis methods and efforts were briefly reviewed. Human error analysis method applied to NPP design has been THERP and ASEP mainly utilizing Swain's HRA handbook, which has not been facilitated enough to put the varied characteristics of MMI into HRA process. The basic concepts on human errors and the system safety approach were revisited, and adopted the process of FMEA with the new definition of Error Segment (ESJ. A modified human error analysis process was suggested. Then, the suggested method was applied to the failure of manual pump actuation through LCD touch screen in loss of feed water event in order to verify the applicability of the proposed method in practices. The example showed that the method become more facilitated to consider the concerns of the introduction of advanced MMI devices, and to integrate human error analysis process not only into HRA/PRA but also into the MMI and interface design. Finally, the possible extensions and further efforts required to obtain the applicability of the suggested method were discussed.

• KSII Transactions on Internet and Information Systems (TIIS)
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• v.16 no.5
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• pp.1516-1539
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• 2022

This article shows a set of physical information fusion IoT systems that we designed for smart buildings. Its essence is a computer system that combines physical quantities in buildings with quantitative analysis and control. In the part of the Internet of Things, its mechanism is controlled by a monitoring system based on sensor networks and computer-based algorithms. Based on the design idea of the agent, we have realized human-machine interaction (HMI) and machine-machine interaction (MMI). Among them, HMI is realized through human-machine interaction, while MMI is realized through embedded computing, sensors, controllers, and execution. Device and wireless communication network. This article mainly focuses on the function of wireless sensor networks and MMI in environmental monitoring. This function plays a fundamental role in building security, environmental control, HVAC, and other smart building control systems. The article not only discusses various network applications and their implementation based on agent design but also demonstrates our collaborative information fusion strategy. This strategy can provide a stable incentive method for the system through collaborative information fusion when the sensor system is unstable in the physical measurements, thereby preventing system jitter and unstable response caused by uncertain disturbances and environmental factors. This article also gives the results of the system test. The results show that through the CPS interaction of HMI and MMI, the intelligent building IoT system can achieve comprehensive monitoring, thereby providing support and expansion for advanced automation management.

• Proceedings of the Korean Nuclear Society Conference
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• 1995.10a
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• pp.117-122
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• 1995

An Integrated Test Facility(ITF) is a human factors experimental environment to evaluate an advanced man machine interface(MMI) design. The ITF includes a human machine simulator(HMS) comprised of a nuclear power plant function simulator, man-machine interface, experiment control station for the experiment control and design, human behavioural data measurement system, and data analysis and experiment evaluation supporting system(DAEXESS). The most important features of ITF is to secure the flexibility and expandibility of Man Machine Interlace(MMI) design to change easily the environment of experiments to accomplish the experiment's objects In this paper, we describe a development scope and characteristics of the ITF such as, hardware and software development scope and characteristics, system thermohydraulic modelling characteristics, and experiment station characteristics for the experiment variables design and control, to be used as an experiment environment for the evaluation of VDU-based control room.

• Proceedings of the KSPS conference
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• 2007.05a
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• pp.41-44
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• 2007

In this paper, we introduce a system in which car navigation scenario is plugged multimodal interface based on multimodal middleware. In map-based system, the combination of speech and pen input/output modalities can offer users better expressive power. To be able to achieve multimodal task in car environments, we have chosen SCXML(State Chart XML), a multimodal authoring language of W3C standard, to control modality components as XHTML, VoiceXML and GPS. In Network Manager, GPS signals from navigation software are converted to EMMA meta language, sent to MultiModal Interaction Runtime Framework(MMI). Not only does MMI handles GPS signals and a user's multimodal I/Os but also it combines them with information of device, user preference and reasoned RDF to give the user intelligent or personalized services. The self-simulation test has shown that middleware accomplish a navigational multimodal task over multiple users in car environments.

• Proceedings of the Korean Institute of Information and Commucation Sciences Conference
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• v.9 no.1
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• pp.462-466
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• 2005

Dynamic (On-line) signature verification system consists of preprocessing, feature extraction, comparison and decision process for internal processing, and registration and verification windows for the user interface. We describe an implementation and design for an advanced dynamic signature verification system. Also, we suggest the method of feature extraction, matching algorithm, efficient user interface and an objective criteria for evaluating the performance.

• Proceedings of the Korean Information Science Society Conference
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• 2004.04b
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• pp.394-396
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• 2004

원자력 산업계에서는 원전 MMIS(Man-Machine Interface System)의 디지털 기술 적용을 위해 많은 노력을 기울이고 있고, 특히 원자력 산업의 특수성인 안전성 확보에 필요한 개발기준과 규제방법 정립에 많은 연구가 수행되고 있다. 또한 디지털 MMIS의 핵심기반기술인 고 신뢰도 소프트웨어 개발 방법론이 확립되지 못하여 소프트웨어 공통모드고장 문제, 정량적인 소프트웨어 신뢰도 보장 문제 등이 현안으로 제기되고 있다. 이와 같이 원전 MMIS의 디지털화를 성공하기 위해서는 소프트웨어의 고 신뢰도 확보가 관건이며, 고 신뢰도를 확보하기 위한 소프트웨어 개발 방법론의 정립이 절실히 요구되고 있다. 본 논문에서는 원전 소프트웨어 개발에 적응되는 규제지침을 분석하고, 일체형원자로(SMART, System-integrated Modular Advanced ReacTor) MMIS 소프트웨어 개발에 적응될 소프트웨어 개발 방법론을 제시한다.

• Proceedings of the Korea Information Processing Society Conference
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• 2004.05a
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• pp.293-296
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• 2004

원자력 산업계에서는 원전 MMIS(Man-Machine Interface System)의 디지털 기술 적용을 위해 많은 노력을 기울이고 있고, 디지털 MMIS의 핵심기반기술인 고 신뢰도 소프트웨어 개발 방법론이 확립되지 못하여 소프트웨어 공통모드고장 문제, 정량적인 소프트웨어 신뢰도 보장 문제 등이 현안으로 제기되고 있다. 이에 따라 원자력 산업의 특수성인 안전성 확보에 필요한 개발기준과 규제방법 정립에 많은 연구가 수행되고 있다. 또한 이와 같이 원전 MMIS의 디지털화를 성공하기 위해서는 소프트웨어의 고 신뢰도 확보가 관건이며, 고 신뢰도와 품질을 확보하기 위한 소프트웨어 개발 지침의 정립이 요구되고 있다. 본 논문에서는 원전 소프트웨어 개발에 적용되는 규제 요건을 분석하고, SMART(System-integrated Modular Advanced ReacTor) MMIS 소프트웨어 개발에 적용될 소프트웨어 개발 지침을 제시한다

• Journal of the Society of Disaster Information
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• v.16 no.4
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• pp.670-681
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• 2020

Purpose: This study aims to derive a PGV prediction equation and to enhance the application of the Onsite EEW technology which has developed through previous studies. Method: The prediction equation for the Onsite EEW derived from earthquake data M≥3.0 and MMI≥II over the past four years. Local seismic risk is estimated using M and PGV deduced from P wave properties. Result: The improved PGV prediction equation estimated the MMI with an average accuracy of 94.8% and the 𝜏_c : Pd method also showed valid performance for alerting local seismic risks. Conclusion: Onsite EEW technology is successfully applied to Korea, and becomes to reduce the blind zone to about 14km.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05a
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• pp.374-379
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• 1996

경보 처리 시스템 (Alarm Processing System)은 발전소의 이상 상태를 검출하여 운전원에게 알려 적절한 조치를 취하게 함으로써 발전소의 상태를 안전하게 유지하도록 하는 운전지원시스템이다. 본 논문은 이러한 목적을 보다 효과적으로 달성하기 위하여 경보 처리 시스템을 경보 생성과 경보 분류, 경보 표시의 3 단계로 설계하였으며, 이를 기반으로 능동 데이터베이스 (Active Database)의 능동 기능을 이용한 개선된 경보 처리 시스템 (Advanced Active Alarm Processing System)을 개발하였다. AAAPS는 데이터 입력의 변경에 대하여 모듈화된 경보 처리 프로그램을 능동적으로 수행시키며 생성된 경보는 윈도우를 이용한 개선된 MMI (Man Machine Interface)로 운전원에게 제공한다.