• International Journal of Aeronautical and Space Sciences
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• v.1 no.2
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• pp.50-67
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• 2000

The spacecraft simulator is used for command validation, operational check of the Satellite Operation Subsystem (SOS), spacecraft anomaly analysis support, satellite operator training etc. In this paper, S/W design features and modeling characteristics of the KOMPSAT Spacecraft Simulator Subsystem (SIM) are described. Validation procedures and simulation results are also provided. The SIM provides extensive simulation capabilities by including models for most of the spacecraft subsystems. The software structure of the SIM was designed and implemented so as to support operations not only in real-time but also in non real-time by utilizing the Hewlett Packard (HP) UNIX functions. The SIM incorporates as many user-friendly Man Machine Interface (MMI) windows as possible so that all the SIM normal operations can be executed through the MMI windows.

• 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.

• Proceedings of the Korean Nuclear Society Conference
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• 2005.05a
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• pp.1307-1308
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• 2005

• Proceedings of the Korea Information Processing Society Conference
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• 2004.05a
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• pp.289-292
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• 2004

원자력발전소 MMIS(Man-Machine Interface System)는 발전소 공정과 관련 장비들을 감시 및 제어하고, 필요시에 보호기능을 수행함으로써 발전소를 안전하고 신뢰성 있게 운전할 수 있도록 지원하고 있다. 그러한 MMIS의 설계에 소프트웨어기반의 컴퓨터 기술이 사용된 경우, 그 설계를 구현하기 위해 사용된 소프트웨어가 설계 및 프로그래밍 오류에 취약하여, 공통유형의 소프트웨어 오류로 인해 하드웨어로써 구축된 다중성 설계를 파기시킬 수 있기 때문에 원자력 발전소의 안전 및 안정 운전과 직결되게 된다. 또한 소프트웨어는 설계공정 결함이 일반적으로 최종 결과물에서 확인될 수 있다는 점 때문에 확인 및 검증기술을 정립하고 체계적인 적용이 필수적이다. 이에 따라 본 논문에서는 현재 설계를 진행중인 SMART(System-integrated Modular Advanced ReacTor) MMIS 소프트웨어를 개발하기 위해 적용되는 확인 및 검증 규제요건을 분석하고, 소프트웨어 개발생명주기에 따른 확인 및 검증을 체계적으로 수행하기 위한 프레임웍을 제시한다.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.11a
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• pp.191-196
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• 1996

The potential value of the Application Specific Integrated Circuits(ASIC's) in safety systems of Nuclear Power Plants(NPP's) is being increasingly recognized because they are essentially hardwired circuitry on a chip, the reliability of the system can be proved more easily than that of software based systems which is difficult in point of software V&V(Verification and Validation). There are two types of ASIC, one is a full customized type, the other is a half customized type. PLD(Programmable Logic Device) used in this paper is a half customized ASIC which is a device consisting of blocks of logic connected with programmable interconnections that are customized in the package by end users. This paper describes the RPS(Reactor Protection System) composed of ASICs which provides emergency shutdown of the reactor to protect the core and the pressure boundary of RCS(Reactor Coolant System) in NPP's. The RPS is largely composed of five logic blocks, each of them was implemented in one PLD, as the followings. A). Bistable Logic B). Matrix Logic C).Initiation Logic D). MMI(Man Machine Interface) Logic E). Test Logic.

• Journal of the Ergonomics Society of Korea
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• v.25 no.3
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• pp.85-96
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• 2006

Main control room(MCR) man-machine interface(MMI) design of advanced nuclear power plants(NPPs) such as APR(advanced power reactor)-1400 can be validated through performance-based tests to determine whether it acceptably supports safe operation of the plant. In this work, plant performance, personnel task, situation awareness, workload, teamwork, and anthropometric/physiological factor are considered as factors for the human performance evaluation. For development of measures in each of the factors, techniques generally used in various industries and empirically proven to be useful are adopted as main measures and some helpful techniques are developed in order to complement the main measures. Also the development of the measures is addressed based on the theoretical background. Finally we discuss the way in which the measures can be effectively integrated and then HUPESS(HUman Performance Evaluation Support System) which is in development based on the integrated way is briefly introduced.

• Proceedings of the Korea Information Processing Society Conference
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• 2023.05a
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• pp.510-512
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• 2023

In order to enhance a model's capability for detecting facial expressions, this research suggests a pipeline that makes use of the GradCAM component. The patching module and the pseudo-labeling module make up the pipeline. The patching component takes the original face image and divides it into four equal parts. These parts are then each input into a 2Dconvolutional layer to produce a feature vector. Each picture segment is assigned a weight token using GradCAM in the pseudo-labeling module, and this token is then merged with the feature vector using principal component analysis. A convolutional neural network based on transfer learning technique is then utilized to extract the deep features. This technique applied on a public dataset MMI and achieved a validation accuracy of 96.06% which is showing the effectiveness of our method.