• 한국인터넷방송통신학회논문지
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• 제9권4호
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• pp.145-152
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• 2009

본 우리나라 고리원전 1호기의 주제어실은 2007년에 부분 개선되었고 2013년에 완전 개량형화 될 예정이다. 부분 개선을 통해 원래의 아나로그 설비를 일부 대체하는 디지털 제어설비가 도입되었으며 안전변수표시 장치같이 단독으로 사용되던 전산시스템이 발전소 전산시스템에 통합되었다. 2015년에는 디지털화를 바탕으로 한 한국표준원전주제어실의 개량이 예정되어 있으나 현장 엔지니어와 운전원들은 개량형주제어실에 대해 호의적이지 않은 실정이다. 따라서 현장 운전원과 엔지니어들의 수용성을 제고하고 또한 사용자 인터페이스와 계측제어 구조를 평가하기 위한 표준형원전의 개량형주제어실 모형이 개발되었으며 모형에는 운전원들의 업무 지원성을 향상시킬 수 있도록 화면이 다중 층으로 구성되며 층간에는 상황추종메뉴로 연결되어 있는 P&ID 베이스 디스플레이 시스템이 채택되었다. 이 시스템은 첫 번째 층에는 간략화 된 P&ID가 디스플레이 되고 계속해서 자세한 추가 정보를 디스플레이 할 수 있도록 고안하였다. 디지털 시스템의 신뢰성과 운전성을 고려한 한국표준원전 개량형주제어실(MCR)의 최종형태가 제시되었으며 추가해서 운전에 영향을 미치지 않도록 발전소 정기보수 기간 중에 주제어실 현대화 작업을 수행할 수 있는 방안이 제시되었다.

• 대한인간공학회지
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• 제32권1호
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• pp.27-36
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• 2013

Objective: This paper describes an analysis of electroencephalography(EEG) signals to identify human errors during using digital devices in nuclear power plants(NPPs). Background: The application of an advanced main control room(MCR) has accompanied with lots of changes in different forms and features by virtue of new digital technologies. The characteristics of these digital technologies and devices provide several opportunities for the use of interface management. It can integrate into a compact single workstation in an advanced MCR, allowing workers to operate the plant with minimum physical burden under any operating condition. However these devices may introduce new types of human errors, and thus we need a means to assess and prevent such errors especially those related to digital devices. Method/Conclusion: The EEG data are relatively objective, and thus we introduce several measures to EEG analysis for obtaining the feasibility of human error identification. Application: This study may support to ensure the safety when applying digital devices in NPPs.

• Nuclear Engineering and Technology
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• 제49권2호
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• pp.335-341
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• 2017

The main control room (MCR) in advanced nuclear power plants (NPPs) has changed from analog to digital control system (DCS). Operation and control have become more automated, centralized, and accurate due to the digitalization of NPPs, which has improved the efficiency and security of the system. New issues associated with human reliability inevitably arise due to the adoption of new accident procedures and digitalization of main control rooms in NPPs. The LingAo II NPP is the first digital NPP in China to apply the state-oriented procedure. In order to address issues related to human reliability analysis for DCS and DCS + state-oriented procedure, the Hunan Institute of Technology conducted a research project based on a cooperative agreement with the LingDong Nuclear Power Co. Ltd. This paper is a brief introduction to the project.

• 대한인간공학회지
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• 제32권1호
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• pp.1-7
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• 2013

Objective: This study proposes the application of Ecological Interface Design(EID) method that is effective for situation awareness in digitalized environment. Background: While cognitive interface design method such as Information Rich Display(IRD) is simply focused on existing information for user, EID method helps users' resource to be solved to higher ion task such as diagnostic and problem solving. Method: Using EID method based on Work Domain Analysis (WDA), it was analyzed and designed for Steam Generator(SG) Water Level control process in a digitalized Main Control Room of Nuclear Power Plant. Proposed EID example is evaluated through interviews by expert & operator. Results: The result of expert & operator showed that EID display might give an aid for operator's decision. Conclusion: The results can reduce critical accidental damage that occurred due to cognitive load and so critical human error. Application: This study may be impact on situation awareness study for digitalized interface design.

• 제어로봇시스템학회:학술대회논문집
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• 제어로봇시스템학회 1997년도 한국자동제어학술회의논문집; 한국전력공사 서울연수원; 17-18 Oct. 1997
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• pp.179-182
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• 1997

In a training simulator for power plant, operator's action in the MCR(Main Control Room) are given to plant process and computer system model as an inputs, and the same response as in real power plant is provided in real time. Inter-process communication and synchronization are especially important among various inputs. In the plant simulator, to simulate the digital control system such as FOXBORO SPEC-200 Micro control system, modification and adaptation of control card(CCC) and its continuous display station(CDS) is necessary. This paper describes the modeling and simulation of FOXBORO SPEC-200 Micro control system applied to Younggwang nuclear power plant unit #3 & 4, and its integration process to the full-scope replica type training simulator. In a simulator, display station like CDS of FOXBORO SPEC-200 Micro control system is classified as ITI(Intelligent Type Instrument), which has a micro processor inside to process information and the corresponding alphanumeric display, and the stimulation of ITI limits the important functions in a training simulator such as backtrack, replay, freeze and IC reset. Therefore, to achieve the better performance of the simulator, modification of CDS and special firmware is developed to simulate the FOXBORO SPEC-200 Micro control system. Each control function inside control card is modeled and simulated in generic approach to accept the plant data and control parameter conveniently, and debugging algorithms are applied for massive coding developed in short period.

• 제어로봇시스템학회논문지
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• 제4권3호
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• pp.392-399
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• 1998

A full-scope replica type simulator whose MCR(main control room) has the same features and operation functions as MCR of the reference power plant has been developed for a fossil power plant. This simulator was developed with the model of Poryung Fossil Power Plant #3,4 which is the standard model of the Korean fossil power plant. It is the first localized simulator for the supercritical, variable boiler pressure type fossil power plant. The simulator provides various kinds of accidents which are in normal plant operation and thus enables operators to recover or reduce possible damages. To design and develop this kind of simulator, we need to integrate high technologies such as system analysis, plant operation and system integration of mechanics, physics, computer science. CASE(Computer Aided Software Engineering) tools were used to develop the dynamic model. This simulator will greatly contribute to the improvement of the safety and efficiency of the fossil power plant by implementing operator training. In this paper, the outline of software and hardware configuration and characteristics of the simulator are described, and the results of 30%, 50%, 75%, 100% load operation test will be discussed.

• 전력전자학회:학술대회논문집
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• 전력전자학회 2000년도 전력전자학술대회 논문집
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• pp.452-455
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• 2000

본 논문에서는 현재 수행중인 가상현실 기술을 이용한 컴퓨터 지원 교육훈력 시스템(CATS : Computer Assister Training System) 개념 설계를 바탕으로 발전소 3D 그래픽 모델을 작성하고 가상현실도구를 사용하여 정보의 변경 및 가공처리로 가상발전소(Virtual Plant) 및 가상판넬(Virtual Panel)상세설계 및 구현결과에 대해 서술한다. 이를 통해 발전소 주요계통 설비 및 발전소 본관 내부의 주요기기 등을 Navigation 할수 있고 이에 대한 엔지니어링 데이터베이스 환경을 작성하여 추후 정확하고 신속한 계통 설비 및 주요기기 정보를 얻을수 있도록 하였으며 가상판넬(Virtual Pannel)을 만들어 학생들이 시뮬레이터실로 가지 않고 MCR(Main Control Room)에서 발전소를 운전하는 것과 같은 효과를 강의실에서 얻을 수 있다.

• 한국시뮬레이션학회:학술대회논문집
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• 한국시뮬레이션학회 1998년도 The Korea Society for Simulation 98 춘계학술대회 논문집
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• pp.86-90
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• 1998

The safety and reliability of nuclear power plant operations relies heavily on the plant operators ability to respond to various emergency situations. It has become standard industry practice to utilize simulators to improve the safety and reliability of nuclear power plants operations. The simulators built for Younggwang#3,4, which is the basic model of the Korean Nuclear Power Plant design, has been developed precisely for this purpose. Dynamic Model and Display Model are developed under US3(UNIX Simulation Software Support System) environment in simulator for Younggwang#3,4. Since these two models are developed under each own operating system, it is necessary to develop a method for transporting data between these two systems. This paper descirves communication environment between Dynamic Model and Display Model, and addresses a file generation method for the Display Model, which will be necessary for designing MMI of MCR(Main Control Room) in the furture.

• 한국시뮬레이션학회논문지
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• 제6권1호
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• pp.85-96
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• 1997

Designing and constructing a proper simulator for real power plants requires extensive research in human engineering and computer science and integration of different fields of technologies such as system analysis, operational knowledge for nuclear plant, etc. A full scope replica type simulator for nuclear power plant is developed. The simulator has the same feature and operational functions as one in the main control room (MCR) of a reference power plant. The simulator provides the necessary training to recover or reduce damages from accidents that usually are unpredictable. This paper describes the configurations and characteristics for the simulator that is developed for Younggwang Nuclear Power Plant #3,4 which is the basic model of the Korean Nuclear Power Plant. The paper also describes technical aspects of Auto Code Generator that is used for developing the simulator. The successful development of the simulator will contribute to improve safety in operation of nuclear power plants.

• 대한인간공학회지
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• 제25권3호
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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.