• 제목/요약/키워드: Nuclear Power Plant I&C Systems

검색결과 42건 처리시간 0.023초

원전 디지털 I&C 계통 고장예측을 위한 신뢰도 함수 추정 인공지능 모델 비교연구 (Comparative Study of AI Models for Reliability Function Estimation in NPP Digital I&C System Failure Prediction)

  • 이대영;이정훈;양승혁
    • 한국산업정보학회논문지
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    • 제28권6호
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    • pp.1-10
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    • 2023
  • 원전 계측제어계통은 정상운전 시 자가 진단기능의 유지보수를 위해 일정 주기로 건전성을 확인하고 있으며, 계획예방정비 기간 동안 기능 및 성능점검을 실시하여 필요한 경우 유지보수를 하고 있다. 하지만 원전의 정보를 계측하고 제어하는 계측제어계통에서도 선제적으로 고장을 진단하고 대처하여 사고전파를 방지할 수 있는 기술개발이 필요하다. 이에 본 논문에서는 계측제어 장비의 환경조건과 자가 진단 데이터를 활용한 신뢰도 함수 추정 방안을 연구하였으며, 고장데이터의 획득을 위해 계측제어 장비의 부품에 대한 Feature 별 확률분포를 가정하여 가상 고장데이터를 생산하였다. 이러한 고장데이터를 바탕으로 생존분석에서 활용되는 대표적인 인공지능 모델(DeepSurve, DeepHit)을 이용하여 신뢰도 함수를 추정하였고, 그와 동시에 전통적인 준모수적 방법론인 Cox 회귀모델을 통해 신뢰도 함수를 추정하여 환경조건과 진단 데이터를 바탕으로 한 잔여 수명 계산을 통해 적용 가능성을 확인하였다.

Development of a Mass Estimation Algorithm Using the Impact Test Data of Nuclear Power Plant

  • Kim, J.S.;I.K. Hwang;Lee, D.Y.;C.S. Ham;Kim, T.H.
    • Nuclear Engineering and Technology
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    • 제32권3호
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    • pp.227-234
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    • 2000
  • It is known that loose parts in the reactor coolant system (RCS) cause serious damage to the systems. This paper is concerned with estimating the mass of a loose part in the steam generator of a nuclear power plant. We developed the mass estimation algorithm based on the Hertz theory in order to estimate the mass of the loose parts and applied the algorithm to the impact test data of YGN3. The mass estimation values were compared with real values in order to verify the algorithm. The result showed that the average error of the mass estimation value is less than 27%.

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AN OVERVIEW OF RISK QUANTIFICATION ISSUES FOR DIGITALIZED NUCLEAR POWER PLANTS USING A STATIC FAULT TREE

  • Kang, Hyun-Gook;Kim, Man-Cheol;Lee, Seung-Jun;Lee, Ho-Jung;Eom, Heung-Seop;Choi, Jong-Gyun;Jang, Seung-Cheol
    • 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.

Processing Alarms in DYNAS: Basic Strategy

  • I. K. Hwang;Kim, J. T.;Lee, D. Y.;N. J. Na;S. J. Song;Park, J. C.;K. C. Kwon;C. S. Ham
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1995년도 추계학술발표회논문집(1)
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    • pp.147-152
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    • 1995
  • During transients or major upsets, operators of a nuclear power plant are faced with a significant amount of information which oftentimes exceeds their capability of processing information in such a time-critical situation. To help resolve this problem of information overload, considerable work is underway worldwide to improve its man-machine interface systems (MMISs). The I&C research team of KAERI is developing a DYNamic Alarm processing System, called DYNAS, to suppress unnecessary or nuisance alarms, and at the same time, emphasize vital information. This paper describes our basic strategy to process alarms in DYNAS.

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원전 계측제어 시스템 보안성환경을 위한 진단기능 평가 (Evaluation of Software Diagnostics for Secure Operational Environment in Nuclear I&C systems)

  • 유성구;설남오
    • 전자공학회논문지
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    • 제53권8호
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    • pp.107-112
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    • 2016
  • 원자력발전소의 안전필수 기능을 수행하는 계측제어 시스템은 원자로의 예상되는 과도상태가 발생되거나 설계기준사고의 결과를 완화하기 위해 원자로 및 주요 기기의 상태를 감시한다. 만일 원자로출력, 냉각재 온도, 또는 증기발생기 수위 등의 상태가 기 정해진 설정치에 도달하게 되면 정확하고 신속하게 원자로를 정지시키는 기능을 수행한다. 이러한 안전필수 시스템은 예상 가능한 사고로부터 인간과 자연을 보호하기 위한 중요 기능을 수행하는 디지털 제어시스템으로써, 비인가 된, 의도되지 않은 변경 등의 취약점으로 인해 신뢰성 있는 운영이 영향을 받지 않도록 보안성환경이 구축되어야 한다. 이러한 보안성환경은 관리적 조치와 기술적 조치를 통해 구현될 수 있다. 본 논문에서는 안전필수 기능을 수행하는 원전 계측제어 시스템의 제어용 소프트웨어 진단기능이 보안성환경을 구축하는 데 효과적인 설계방안인지를 평가하였다. 이를 위해, 제어용 소프트웨어의 무결성을 확인하는 순환잉여검사(CRC) 진단기능에 대한 모의실험을 수행하였다. 본 논문에서의 효과성 평가는 향후 안전필수기능을 수행하는 원전 계측제어 시스템의 설계 및 안전성 분석에 활용될 수 있을 것으로 기대된다.

Damage and vibrations of nuclear power plant buildings subjected to aircraft crash part I: Model test

  • Li, Z.R.;Li, Z.C.;Dong, Z.F.;Huang, T.;Lu, Y.G.;Rong, J.L.;Wu, H.
    • Nuclear Engineering and Technology
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    • 제53권9호
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    • pp.3068-3084
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    • 2021
  • Investigations of large commercial aircraft impact effect on nuclear power plant (NPP) buildings have been drawing extensive attentions, particularly after the 9/11 event, and this paper aims to experimentally assess the damage and vibrations of NPP buildings subjected to aircraft crash. In present Part I, two shots of reduce-scaled model test of aircraft impacting on NPP building were carried out. Firstly, the 1:15 aircraft model (weighs 135 kg) and RC NPP model (weighs about 70 t) are designed and prepared. Then, based on the large rocket sled loading test platform, the aircraft models were accelerated to impact perpendicularly on the two sides of NPP model, i.e., containment and auxiliary buildings, with a velocity of about 170 m/s. The strain-time histories of rebars within the impact area and acceleration-time histories of each floor of NPP model are derived from the pre-arranged twenty-one strain gauges and twenty tri-axial accelerometers, and the whole impact processes were recorded by three high-speed cameras. The local penetration and perforation failure modes occurred respectively in the collision scenarios of containment and auxiliary buildings, and some suggestions for the NPP design are given. The maximum acceleration in the 1:15 scaled tests is 1785.73 g, and thus the corresponding maximum resultant acceleration in a prototype impact might be about 119 g, which poses a potential threat to the nuclear equipment. Furthermore, it was found that the nonlinear decrease of vibrations along the height was well reflected by the variations of both the maximum resultant vibrations and Cumulative Absolute Velocity (CAV). The present experimental work on the damage and dynamic responses of NPP structure under aircraft impact is firstly presented, which could provide a benchmark basis for further safety assessments of prototype NPP structure as well as inner systems and components against aircraft crash.

Feasibility Study on KSNP Adaption of French Digital Protection System

  • Koo, Jun-Mo;Lee, Young-Ryul;Jung, Ho-Chang;Chang, Ik-Ho;Han, Jai-Bok
    • Nuclear Engineering and Technology
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    • 제28권4호
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    • pp.359-365
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    • 1996
  • Upgrade of nuclear power plant I&C systems by using digital technology has been implemented to overcome the obsolescence of existing equipment and improve plant availability in many advanced countries. For upgrade of the Plant Protection System(PPS) based on conventional analog technology in the UCN 3&4 and YGN 5&6, French modernized Digital Integrated Protection System(DIPS) with proven technology is reviewed and evaluated for the adaptability into PPS. This paper contains the results of feasibility study for the design of digital PPS using French DIPS technology. Based on the results of evaluations, the system architecture of digital PPS is designed and described.

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AN ANALYSIS OF TECHNICAL SECURITY CONTROL REQUIREMENTS FOR DIGITAL I&C SYSTEMS IN NUCLEAR POWER PLANTS

  • Song, Jae-Gu;Lee, Jung-Woon;Park, Gee-Yong;Kwon, Kee-Choon;Lee, Dong-Young;Lee, Cheol-Kwon
    • Nuclear Engineering and Technology
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    • 제45권5호
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    • pp.637-652
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    • 2013
  • Instrumentation and control systems in nuclear power plants have been digitalized for the purpose of maintenance and precise operation. This digitalization, however, brings out issues related to cyber security. In the most recent past, international standard organizations, regulatory institutes, and research institutes have performed a number of studies addressing these systems cyber security.. In order to provide information helpful to the system designers in their application of cyber security for the systems, this paper presents methods and considerations to define attack vectors in a target system, to review and select the requirements in the Regulatory Guide 5.71, and to integrate the results to identify applicable technical security control requirements. In this study, attack vectors are analyzed through the vulnerability analyses and penetration tests with a simplified safety system, and the elements of critical digital assets acting as attack vectors are identified. Among the security control requirements listed in Appendices B and C to Regulatory Guide 5.71, those that should be implemented into the systems are selected and classified in groups of technical security control requirements using the results of the attack vector analysis. For the attack vector elements of critical digital assets, all the technical security control requirements are evaluated to determine whether they are applicable and effective, and considerations in this evaluation are also discussed. The technical security control requirements in three important categories of access control, monitoring and logging, and encryption are derived and grouped according to the elements of attack vectors as results for the sample safety system.

원자력발전소 사이버보안 훈련을 위한 HIL(Hardware In the Loop) System 개발 (Development of Hardware In the Loop System for Cyber Security Training in Nuclear Power Plants)

  • 송재구;이정운;이철권;이찬영;신진수;황인구;최종균
    • 정보보호학회논문지
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    • 제29권4호
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    • pp.867-875
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    • 2019
  • 원자력을 포함한 산업제어시스템에 대한 사이버보안 사건이 증가함에 따라 기술적 보안 조치와 더불어 사이버보안교육 훈련 및 사이버 비상사건 대응 훈련이 요구되고 있다. 대상 설비를 운영 관리하는 담당자들에게 효과적인 사이버보안 인식 및 교육 훈련을 위해서는 센서 수준에서부터 발전소 운영 상태까지 사이버공격으로 인한 영향 분석이 가능한 훈련용 시스템이 요구된다. 이에 본 논문에서는 원자력 운영 상태를 모사하는 발전소 시뮬레이션과 특정 계통의 시뮬레이션 및 물리장치를 포함하는 원자력발전소 사이버보안 훈련용 HIL 시스템을 개발하였다. 이를 통해 계통담당자 및 사이버보안조직을 대상으로 하는 기술적 훈련, 사이버보안 조직 및 비상사건대응 조직을 대상으로 하는 특화된 사이버보안 훈련을 지원하고자 한다.

Cyber attack taxonomy for digital environment in nuclear power plants

  • Kim, Seungmin;Heo, Gyunyoung;Zio, Enrico;Shin, Jinsoo;Song, Jae-gu
    • Nuclear Engineering and Technology
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    • 제52권5호
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    • pp.995-1001
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    • 2020
  • With the development of digital instrumentation and control (I&C) devices, cyber security at nuclear power plants (NPPs) has become a hot issue. The Stuxnet, which destroyed Iran's uranium enrichment facility in 2010, suggests that NPPs could even lead to an accident involving the release of radioactive materials cyber-attacks. However, cyber security research on industrial control systems (ICSs) and supervisory control and data acquisition (SCADA) systems is relatively inadequate compared to information technology (IT) and further it is difficult to study cyber-attack taxonomy for NPPs considering the characteristics of ICSs. The advanced research of cyber-attack taxonomy does not reflect the architectural and inherent characteristics of NPPs and lacks a systematic countermeasure strategy. Therefore, it is necessary to more systematically check the consistency of operators and regulators related to cyber security, as in regulatory guide 5.71 (RG.5.71) and regulatory standard 015 (RS.015). For this reason, this paper attempts to suggest a template for cyber-attack taxonomy based on the characteristics of NPPs and exemplifies a specific cyber-attack case in the template. In addition, this paper proposes a systematic countermeasure strategy by matching the countermeasure with critical digital assets (CDAs). The cyber-attack cases investigated using the proposed cyber-attack taxonomy can be used as data for evaluation and validation of cyber security conformance for digital devices to be applied, and as effective prevention and mitigation for cyber-attacks of NPPs.