• Nuclear Engineering and Technology
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• v.44 no.8
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• pp.929-938
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• 2012

The Computerized Procedure System (CPS) is one of the primary operating support systems in the digital Main Control Room. The CPS displays procedure on the computer screen in the form of a flow chart, and displays plant operating information along with procedure instructions. It also supports operator decision making by providing a system decision. A procedure flow should be correct and reliable, as an error would lead to operator misjudgment and inadequate control. In this paper we present a modeling for the CPS that enables formal verification based on Petri nets. The proposed State Token Petri Nets (STPN) also support modeling of a procedure flow that has various interruptions by the operator, according to the plant condition. STPN modeling is compared with Coloured Petri net when they are applied to Emergency Operating Computerized Procedure. A converting program for Computerized Procedure (CP) to STPN has been also developed. The formal verification and validation methods of CP with STPN increase the safety of a nuclear power plant and provide digital quality assurance means that are needed when the role and function of the CPS is increasing.

• Journal of the Korean Institute of Gas
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• v.22 no.6
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• pp.8-15
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• 2018

worker-centered safety management for hazardous areas in the plant is required. The causes of gas accidents in the past five years are closely related to the behavior of the operator, such as careless handling of the user, careless handling of the suppliers, and intentional, as well as equipment failure and accident of thought. In order to prevent such accidents, real-time monitoring of hazardous areas in the plant is required. However, when installing a camera in a work space for real-time monitoring, problems such as human rights abuse occur. In order to prevent this, an infrared camera with low resolution with low exposure of the operator is used. In real-time monitoring, image analysis is performed using CNN algorithm, not human, to prevent human rights violation.

• Nuclear Engineering and Technology
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• v.51 no.5
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• pp.1307-1313
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• 2019

Recent analysis results with realistic assumptions provide the variability of operator allowable time for the initiation of aggressive cooldown under small break loss of coolant accident or steam generator tube rupture with total failure of high pressure safety injection. We investigated how plant risk may vary depending on the variability of operators' failure probability of timely initiation of aggressive cooldown. Using a probabilistic safety assessment model of a nuclear power plant, we showed that plant risks had a linear relation with the failure probability of aggressive cooldown and could be reduced by up to 10% as aggressive cooldown is more reliably performed. For individual accident management, we found that core damage potential could be gradually reduced by up to 40.49% and 63.84% after a small break loss of coolant accident or a steam generator tube rupture, respectively. Based on the importance of timely initiation of aggressive cooldown by main control room operators within the success criteria, implications for improvement of emergency operating procedures are discussed. We recommend conducting further detailed analyses of aggressive cooldown, commensurate with its importance in reducing risks in nuclear power plants.

• Nuclear Engineering and Technology
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• v.56 no.3
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• pp.866-872
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• 2024

Design Extension Conditions (DEC)-A assessments of the operating nuclear power plants are generally considered for the purpose of getting additional safety demonstrations of their capability to undergo conditions that are generally more severe than DBAs by features implemented in the design and accident management measures. The pursued methodology is generally based upon Best Estimate approaches aiming at verifying that the safety limits in terms of integrity of the barriers against eventual large or early releases of radioactive material are fulfilled. These aspects are nowadays being experimentally and analytically addressed within the OECD/NEA experimental projects like the ATLAS and PKL series where a set of DEC-A experiments are considered. In this paper, experiments related to SBLOCA at the vessel upper head of the pressurized vessel of ATLAS and PKL are analytically assessed using the CATHARE code. These experiments includes issues related to common cause failure of the safety injection system and operator actions for preventing core excessive overheating. It is shown that, on the one hand, the safety features embedded in the design together with the operator actions are capable to prevent the progression towards a severe accident state and on the other hand, the code prediction capabilities for such scenario are generally good but still to be enhanced.

• Proceedings of the Korean Operations and Management Science Society Conference
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• 2004.05a
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• pp.664-667
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• 2004

In nuclear power plant, the main control room(MCR) plays a leading and important role, so it is the core to have its design well operater-centered, both physically and cognitively. This paper especially analyzes focusing on lighting MCR environment and shows alternatives. It will lead to improve work efficiency and to care operator's sight. In conclusion, reducing operator's stress, fatigue and increasing safety, comfort.

• Proceedings of KOSOMES biannual meeting
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• 2017.04a
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• pp.33-33
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• 2017

• Journal of the Korean Society of Safety
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• v.7 no.4
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• pp.95-99
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• 1992

The attraction of using expert system in operator support systems for modern plant is that it offers a way of dealing with the problem of information overload that can occur during a severe disturbance at a modern industrial plant. During such a disturance the volume of information presented to operators may be such that they are unable to decide quickly what is important and what is not. Therefore, arriving at a correct diagnosis of the initialling fault may be delayed. An expert system operator sup-port system is a means of focusing attention on what really matters and cutting out the rest. This paper presents the development of prototype expert system which detect the fault part, machine, system and decide action priority. This prototype expert system has 6 sub- system which is Interface Manager, Decision Maker, Inference Engine, Knowledge base, Simulatio, and D.P System ( Diagnosis and predictor)

• Proceedings of the KSR Conference
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• 2008.06a
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• pp.407-416
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• 2008

The OCC of Seoul Metro whose operation began in 1974 is in charge of conveying 4,000,000 passengers across 117 subway stations in travel zones of 134.9Km in length. It continues to strive to ensure passenger safety by applying state-of-the-art-technology to each control system without delay. The power control center especially designed to provide power system operations for all stations of Seoul Metro(Line 1 to 4) and the rolling stocks implements preventive safety systems with the real time power system operational information on changes in conditions from the field through the power SCADA system(41 substations, 117 stations, 137 terminal units). This paper reports the differences of each line's power SCADA system(power SCADA systems of Seoul Metro(Line 1 to 4)), the roles and functions of the system, and the system operating characteristics and limits from the standpoint of the operator.

• Proceedings of the KSR Conference
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• 2008.06a
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• pp.2325-2331
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• 2008

This article is about a new law of railroad industry has come into effect in 2004 and that left the railroad company operated under the private system. Accordingly, it has to encounter a variety of managers on the railroad safety part too. Incheon Airport Railroad that was, from Incheon International Airport to Kimpo Airport, opened to traffic on the 23th March, 2007 as the first private railroad company in Korea. This railroad company is working hard to be a safe and convenient airport railroad. There is not operated an effective emergency response that the railroad company and the emergency response personnel without standard operation procedure, recently. The original emergency manual and the emergency procedure of the synthesized railroad safety development business. I am proposing to establish the emergency response scenario according to the different situations that the train operator.

• Nuclear Engineering and Technology
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• v.44 no.4
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• pp.415-420
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• 2012

It is important to understand the amount of time required to execute an emergency procedural task in a high-stress situation for managing human performance under emergencies in a nuclear power plant. However, the time to execute an emergency procedural task is highly dependent upon expert judgment due to the lack of actual data. This paper proposes an analytical method to estimate the operator's performance time (OPT) of a procedural task, which is based on a measure of the task complexity (TACOM). The proposed method for estimating an OPT is an equation that uses the TACOM as a variable, and the OPT of a procedural task can be calculated if its relevant TACOM score is available. The validity of the proposed equation is demonstrated by comparing the estimated OPTs with the observed OPTs for emergency procedural tasks in a steam generator tube rupture scenario.