• 대한전기학회:학술대회논문집
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• 대한전기학회 2007년도 제38회 하계학술대회
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• pp.50-51
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• 2007

과거 단일 회사로 구성된 전력산업 체제하에서의 신뢰도에 대한 인식과 중요성들이 전력시장과 경쟁이 도입된 다각화된 이해 주체들 이 존재하는 현행의 국내 전력산업 구조에서는 서로 다른 양상을 띄고 변화하고 있다. 전원 및 송?변전 시설계획에서부터 계통운영 계획 및 실시간 급전에 이르기까지 연속선상의 계통운영 업무에 있어 전력공급의 안정성 확보와 더불어 보다 합리적이고 효율적인 또는 경제적인 계획과 운영에 대한 요구(Needs)가 기존의 결정론적인 신뢰도 평가의 다각적 접근 즉, 확률론적인 신뢰도평가 기법을 개발하게 하였으며, 이에 미국 전력중앙연구소(EPRI)의 PRA(Probabilistic Reliability Assessment) S/W를 도입하여 실제 계통운영의 단위업무와 접목하여 리스크를 고려한 계통안전도평가 구현의 잠재적 가능성과 극복해야 할 한계를 파악하였다.

• Nuclear Engineering and Technology
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• 제41권6호
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• pp.849-858
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• 2009

Risk caused by safety-critical instrumentation and control (I&C) systems considerably affects overall plant risk. As digitalization of safety-critical systems in nuclear power plants progresses, a risk model of a digitalized safety system is required and must be included in a plant safety model in order to assess this risk effect on the plant. Unique features of a digital system cause some challenges in risk modeling. This article aims at providing an overview of the issues related to the development of a static fault-tree-based risk model. We categorize the complicated issues of digital system probabilistic risk assessment (PRA) into four groups based on their characteristics: hardware module issues, software issues, system issues, and safety function issues. Quantification of the effect of these issues dominates the quality of a developed risk model. Recent research activities for addressing various issues, such as the modeling framework of a software-based system, the software failure probability and the fault coverage of a self monitoring mechanism, are discussed. Although these issues are interrelated and affect each other, the categorized and systematic approach suggested here will provide a proper insight for analyzing risk from a digital system.

• 기록학연구
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• 제9호
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• pp.164-189
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• 2004

This paper illustrates preliminary modeling for University Archives Management System(UAMS) construction. University must install Intermediate Archives(records and archives) facilities and management system by Public Records and Archives Act(PRA). But it is very difficult to generalize UAMS because University co-exists public and its own characteristic. For UAMS modeling, this paper first identifies University document's production creators and documental boundary. Then it is studied how University archives management is operated and what archives system by PRA means in University. Second systematic connection plan of Intermediate Archives(records and archives) facilities and manuscripts management is surveyed through National Universities and complementary things are presented. Finally through the above study UAMS model is suggested as future-oriented University archives management. UAMS model suggested from this study includes as follows. First manuscripts management as present Records and Archives system's standard function extension. Second manuscripts management system as system management area's extension using in Universities. It is desirable to extend to expert archives system. Finally integrated operating system model for using actively records, archives and manuscripts management systems operating in Universities.

• Nuclear Engineering and Technology
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• 제54권3호
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• pp.896-908
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• 2022

As a part of probabilistic risk (or safety) assessment (PRA or PSA) of nuclear power plants (NPPs), the primary role of human reliability analysis (HRA) is to provide credible estimations of the human error probabilities (HEPs) of safety-critical tasks. In this regard, it is vital to provide credible HEPs based on firm technical underpinnings including (but not limited to): (1) how to collect HRA data from available sources of information, and (2) how to inform HRA practitioners with the collected HRA data. Because of these necessities, the U.S. Nuclear Regulatory Commission and the Korea Atomic Energy Research Institute independently developed two dedicated HRA data collection systems, SACADA (Scenario Authoring, Characterization, And Debriefing Application) and HuREX (Human Reliability data EXtraction), respectively. These systems provide unique frameworks that can be used to secure HRA data from full-scope training simulators of NPPs (i.e., simulator data). In order to investigate the applicability of these two systems, two papers have been prepared with distinct purposes. The first paper, entitled "SACADA and HuREX: Part 1. The Use of SACADA and HuREX Systems to Collect Human Reliability Data", deals with technical issues pertaining to the collection of HRA data. This second paper explains how the two systems are able to inform HRA practitioners. To this end, the process of estimating HEPs is demonstrated based on feed-and-bleed operations using HRA data from the two systems.

• Nuclear Engineering and Technology
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• 제54권5호
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• pp.1686-1697
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• 2022

As a part of probabilistic risk (or safety) assessment (PRA or PSA) of nuclear power plants (NPPs), the primary role of human reliability analysis (HRA) is to provide credible estimations of the human error probabilities (HEPs) of safety-critical tasks. Accordingly, HRA community has emphasized the accumulation of HRA data to support HRA practitioners for many decades. To this end, it is critical to resolve practical problems including (but not limited to): (1) how to collect HRA data from available information sources, and (2) how to inform HRA practitioners with the collected HRA data. In this regard, the U.S. Nuclear Regulatory Commission (NRC) and Korea Atomic Energy Research Institute (KAERI) independently initiated two large projects to accumulate HRA data by using full-scale simulators (i.e., simulator data). In terms of resolving the first practical problem, the NRC and KAERI developed two dedicated HRA data collection systems, SACADA (Scenario Authoring, Characterization, And Debriefing Application) and HuREX (Human Reliability data EXtraction), respectively. In addition, to inform HRA practitioners, the NRC and KAERI proposed several ideas to extract useful information from simulator data. This paper is the first of two papers to discuss the technical underpinnings of the development of the SACADA and HuREX systems.

• Journal of Radiation Protection and Research
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• 제30권2호
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• pp.91-97
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• 2005

베이지안 기법은 객관적 자료 이외에 주관적 지식도 평가에 반영하는 특성으로 인해 최근 PRA에서 널리 사용되고 있다. 본 연구에서는 비파괴검사 장비 분실에 대한 방사선 위험도를 평가하기 위해 베이지안 기법을 활용하였다. U.S. NRC에서 제시한 선원분실 피폭 시나리오를 국내 실정에 맞게 재구성하였고 안전인자의 사고발생 확률에 국한하여 적용하였다. 사고발생 확률수정의 경우 Jeffreys사전분포를 사용한 결과가 모호사전분포를 사용한 결과보다 5 % 베이즈 하한치가 더 낮아서 방사선 사고와 같은 낮은 사고발생 확률을 가지는 시스템에 대한 위험도 평가에 적합하다. 위험도의 결과를 보면 일반인의 연간 예상되는 평균선량은 베이지안 기법이 고전적인 기법에 의거한 평가보다 높은 선량을 나타내는데 이는 수정된 안전인자 확률의 평균이 고전적 확률 참보다 높게 평가된 것에 기인한다. 국내의 경우 방사선 위험도 평가를 위한 자료구축이 미비한 바 베이지안 기법은 위험도 평가에 유용한 대안으로 활용할 수 있으며 이러한 연구는 위험도 정보-기반 규제에 기여할 것이다.

• Nuclear Engineering and Technology
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• 제53권8호
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• pp.2534-2546
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• 2021

Nuclear emergency preparedness and response is an essential part to ensure the safety of nuclear power plant (NPP). Key support technologies of nuclear emergency decision-making usually consist of accident diagnosis, source term estimation, accident consequence assessment, and protective action recommendation. Source term estimation is almost the most difficult part among them. For example, bad communication, incomplete information, as well as complicated accident scenario make it hard to determine the reactor status and estimate the source term timely in the Fukushima accident. Subsequently, it leads to the hard decision on how to take appropriate emergency response actions. Hence, this paper aims to develop a method for rapid source term estimation to support nuclear emergency decision making in pressurized water reactor NPP. The method aims to make our knowledge on NPP provide better support nuclear emergency. Firstly, this paper studies how to build a Bayesian network model for the NPP based on professional knowledge and engineering knowledge. This paper presents a method transforming the PRA model (event trees and fault trees) into a corresponding Bayesian network model. To solve the problem that some physical phenomena which are modeled as pivotal events in level 2 PRA, cannot find sensors associated directly with their occurrence, a weighted assignment approach based on expert assessment is proposed in this paper. Secondly, the monitoring data of NPP are provided to the Bayesian network model, the real-time status of pivotal events and initiating events can be determined based on the junction tree algorithm. Thirdly, since PRA knowledge can link the accident sequences to the possible release categories, the proposed method is capable to find the most likely release category for the candidate accidents scenarios, namely the source term. The probabilities of possible accident sequences and the source term are calculated. Finally, the prototype software is checked against several sets of accident scenario data which are generated by the simulator of AP1000-NPP, including large loss of coolant accident, loss of main feedwater, main steam line break, and steam generator tube rupture. The results show that the proposed method for rapid source term estimation under nuclear emergency decision making is promising.

• 전자통신동향분석
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• 제7권4호
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• pp.107-114
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• 1992

본 고에서는 Bellcore 에서 제시한 ISDN 의 신뢰도 및 가용도를 BRA(Basic Rate Access) 와 PRA(Primary Rate Access) 각각에 대해서 살펴보았다 또한 표준의사접속 (HRC : Hypothetical Reference Connection) 을 근간으로 해서 ISDN 의 신뢰도 목표치와 가용도 목표치를 제시하였다 Bellcore에서 제시한 ISDN 스위칭 시스팀의 신뢰도 성능 목표치는 22개의 신뢰도 파라미터와 목표치로 정의 되었으며, 22개의 신뢰도 파라미터 는 Downtimes, cutoff call probability, Ineffective machine attempt(IMA) probability 와 Failure intensity 등 4개의 종류로 나누어서 제시하였다.

• 제어로봇시스템학회:학술대회논문집
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• 제어로봇시스템학회 1988년도 한국자동제어학술회의논문집(국내학술편); 한국전력공사연수원, 서울; 21-22 Oct. 1988
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• pp.178-182
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• 1988

In this study, the motion compensating interpolation algorithm is presented. The presented algorithm allows the unblutted reconstruction of omitted frames. It is shown that the Walker & Rao's estimation algorithm using modified displaced frame difference combined with rectangulat adaptive measurement window increases the reliability of the estimation results. The remark ably improved image quality is achieved by change detection and segmentation.

• 한국생명과학회:학술대회논문집
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• 한국생명과학회 2005년도 국제학술심포지움 The 44th Annual Meeting of Korean Society for Life Science
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• pp.122-122
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• 2005