• Title/Summary/Keyword: 주기적안전성평가

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The Software Reliability Evaluation of a Nuclear Controller Software Using a Fault Detection Coverage Based on the Fault Weight (가중치 기반 고장감지 커버리지 방법을 이용한 원전 제어기기 소프트웨어 신뢰도 평가)

  • Lee, Young-Jun;Lee, Jang-Soo;Kim, Young-Kuk
    • KIPS Transactions on Computer and Communication Systems
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    • v.5 no.9
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    • pp.275-284
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    • 2016
  • The software used in the nuclear safety field has been ensured through the development, validation, safety analysis, and quality assurance activities throughout the entire process life cycle from the planning phase to the installation phase. However, this evaluation through the development and validation process needs a lot of time and money, and there are limitations to ensure that the quality is improved enough. Therefore, the effort to calculate the reliability of the software continues for a quantitative evaluation instead of a qualitative evaluation. In this paper, we propose a reliability evaluation method for the software to be used for a specific operation of the digital controller in a nuclear power plant. After injecting weighted faults in the internal space of a developed controller and calculating the ability to detect the injected faults using diagnostic software, we can evaluate the software reliability of a digital controller in a nuclear power plant.

Development of Evaluation Factors for Breakwater Rehabilitation (방파제 성능개선을 위한 평가항목 개발)

  • Park, Su-Yeul;Yun, Won-Gun;Kang, Go-Une;Kim, Seok
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.22 no.4
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    • pp.67-74
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    • 2021
  • Domestically, technical condition evaluation for breakwaters has been conducted through safety checks and safety diagnosis. If necessary, maintenance for the facility is conducted. However, in recent years, the need for infrastructure management has been increasing from a life-cycle-cost perspective. For these reasons, the "Sustainable Infrastructure Management Basic Act" was enacted. Previously, only the technical part of the breakwaters was evaluated. However, based on the act, comprehensive management of breakwaters will be possible through performance improvement by adding economic and political evaluations. In this study, evaluation factors and evaluation methods were developed for a breakwater rehabilitation project. The purpose of this study is to present a development direction, items, and methods for the evaluation of breakwater performance improvement to be applied in future practice. This study reviews the concept of maintenance and performance improvement, the literature related to performance improvement, and the project type for the common standard of performance improvement. Evaluation items and evaluation methods for breakwater rehabilitation are suggested to be reviewed by experts. The methodology suggested in this study could be used for preventive maintenance and to reduce accidents.

로듐 자기 기전력형 중성자 계측기의 수명 연장에 관한 연구

  • 김성래;김길곤;김정식;박성훈;권종수;박현우
    • Nuclear Engineering and Technology
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    • v.27 no.6
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    • pp.911-917
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    • 1995
  • 로듐 자기 기전력형 중성자 계측기는 단위 중성자당 발생되는 전류 신호가 매우 커 계측성이 우수하나 연소율이 빨라 자주 교체해야 하므로 재장전 기간 연장 및 새로운 로듐계측기 구입 등의 문제점이 있다. 75% 연소에 해당하는 제5핵 연료 주기 기간 동안 영광 3, 4호기와 같은 C-E 원자로에 사용되고 있는 로듐 자기 기전력형 중성자 계측기의 연소 거동이 C-E에 의해서 연구되었다. 약 제3핵연료주기까지 분석한C-E의 초창기 연구에서는 중성자 방사화율 개념에 근거하여 약 66%연소시점까지 로듐계측기 연소특성곡선은 선형적임이 밝혀진 바 있다. [l, 2] 그 후 C-E의 연구에 의하면 약 75% 연소에 해당하는 제5핵연료 주기까지도 로듐계측기 연소 특성 곡선은 선형적임이 밝혀졌다. 그 결과로 C-E형 원자력발전소에서 사용되는 로듐 노내계측기의 수명을 약 60%연소에서 66%연소 시점까지 연장시킬 수 있게 되었다. [3]이 정도의 계측기 수명 연장은 약 반년의 원자로 운전 기간에 해당되며 차기 핵연료주기에서 많은 로듐 노내계측기를 계속 사용할 수 있게 한다. 특히 영광 3, 4호기가 12개월 핵연료 주기에서 18개월 핵연료 주기로 재장전 전략을 바꿀 경우 로듐 노내계측기의 수명 이 연장되지 않으면 계측기 교체가 빈번해 질 것으로 사료되어 로듐 수명 연장과 관련된 기술 특히 C-E 및 B&W의 로듐 노내계측기 연소도 특성곡선 불확실도 평가 및 출력 측정 계통 오차 분석 기술을 소개하고자 한다. 영광3, 4호기에서 사용중인 로듐 노내계측기 수명을 현재 연소도 기준 66%내로 한정하고 있는데 C-E 및 B&W의 로듐 노내계측기연소 특성에 관한 연구 내용을 분석한 결과 노내계측기 수명을 연소도가 66%를 초과하는 계측기가 있어도 전체적으로 불확실도가 안전한계를 넘지 않으면 노내상주가 가능한 것으로 평가되었다.

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Early Management of Total Parenteral Nutrition Induced Hepatic Dysfunction with Cyclic Parenteral Nutrition (정맥영양 관련 간기능 장애에서 조기 주기성 정맥영양법의 유용성)

  • Lee, Sung Soo;Chang, Ju Young;Yang, Hye Ran;Ko, Jae Sung;Choi, Kyung Hee;Seo, Jeong Kee
    • Pediatric Gastroenterology, Hepatology & Nutrition
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    • v.7 no.1
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    • pp.61-73
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    • 2004
  • Purpose: Liver function test abnormalities have been reported frequently in patients receiving total parenteral nutrition (TPN). In adults, it is known that liver complications decrease with the use of cyclic parenteral nutrition (CPN), especially if the shift to cycling was not too late. However, there are few studies about the effects of cycling on liver injury in children beyond the neonatal period. The aim of this study is to evaluate the effect of the early use of CPN on total parenteral nutrition induced hepatic dysfunction. Methods: Twelve sets of CPN in 11 children (2 months to 17 years) were included in this study. Data on underlying diseases, age, length of time on TPN, macronutrient intake, complications, and biochemical parameters were collected from clinical records. All children had received CPN in the early period of persistent transaminase elevation or cholestasis complicated by previous continuous PN. The duration of infusion off-time in CPN was 2 hours in patients less than 3 months of age and 4 hours in the older children. Results: All 12 cases showed elevated aminotransferase and 5 of them also showed cholestasis. Serum total bilirubin concentration was normalized in all 5 cases with median periods of 8 days (p<0.05) after initiation of CPN. ALT either decreased significantly or was normalized in all cases with median periods of 30 days (p<0.05) on CPN. The CPN was well tolerated without significant complication except for one case of hyperglycemia. Conclusion: The early use of cyclic parenteral nutrition had a beneficial effect in improving hepatic dysfunction complicated by TPN in children.

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Priority Analysis of Cause Factors of Safety Valve Failure Mode Using Analytical Hierarchy Process (AHP를 활용한 안전밸브(PSV) 고장모드의 Cause Factors 우선순위 분석)

  • Kim, Myung Chul;Lee, Mi Jeong;Lee, Dong Geon;Baek, Jong-Bae
    • Korean Chemical Engineering Research
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    • v.60 no.3
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    • pp.347-355
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    • 2022
  • The safety valve (PSV) is a safety device that automatically releases a spring when the pressure generated by various causes reaches the set pressure, and is restored to a normal state when the pressure falls below a certain level. Periodic inspection and monitoring of safety valves are essential so that they can operate normally in abnormal conditions such as pressure rise. However, as the current safety inspection is performed only at a set period, it is difficult to ensure the safety of normal operation. Therefore, evaluation items were developed by finding failure modes and causative factors of safety valves required for safety management. In addition, it is intended to provide decision-making information for securing safety by deriving the priority of items. To this end, a Delphi survey was conducted three times to derive evaluation factors that were judged to be important in relation to the Failure Mode Cause Factor (FMCFs) of the safety valve (PSV) targeting 15 experts. As a result, 6 failure modes of the safety valve and 22 evaluation factors of its sub-factors were selected. In order to analyze the priorities of the evaluation factors selected in this way, the hierarchical structure was schematized, and the hierarchical decision-making method (AHP) was applied to the priority calculation. As a result of the analysis, the failure mode priorities of FMCFs were 'Leakage' (0.226), 'Fail to open' (0.201), 'Fail to relieve req'd capacity' (0.152), 'Open above set pressure' (0.149), 'Spuriously' 'open' (0.146) and 'Stuck open' (0.127) were confirmed in the order. The lower priority of FMCFs is 'PSV component rupture' (0.109), 'Fail to PSV size calculation' (0.068), 'PSV Spring aging' (0.065), 'Erratic opening' (0.059), 'Damage caused by improper installation and handling' (0.058), 'Fail to spring' (0.053), etc. were checked in the order. It is expected that through efficient management of FMCFs that have been prioritized, it will be possible to identify vulnerabilities of safety valves and contribute to improving safety.

AI를 이용한 차량용 침입 탐지 시스템에 대한 평가 프레임워크

  • Kim, Hyunghoon;Jeong, Yeonseon;Choi, Wonsuk;jo, Hyo Jin
    • Review of KIISC
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    • v.32 no.4
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    • pp.7-17
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    • 2022
  • 운전자 보조 시스템을 통한 차량의 전자적인 제어를 위하여, 최근 차량에 탑재된 전자 제어 장치 (ECU; Electronic Control Unit)의 개수가 급증하고 있다. ECU는 효율적인 통신을 위해서 차량용 내부 네트워크인 CAN(Controller Area Network)을 이용한다. 하지만 CAN은 기밀성, 무결성, 접근 제어, 인증과 같은 보안 메커니즘이 고려되지 않은 상태로 설계되었기 때문에, 공격자가 네트워크에 쉽게 접근하여 메시지를 도청하거나 주입할 수 있다. 악의적인 메시지 주입은 차량 운전자 및 동승자의 안전에 심각한 피해를 안길 수 있기에, 최근에는 주입된 메시지를 식별하기 위한 침입 탐지 시스템(IDS; Intrusion Detection System)에 대한 연구가 발전해왔다. 특히 최근에는 AI(Artificial Intelligence) 기술을 이용한 IDS가 다수 제안되었다. 그러나 제안되는 기법들은 특정 공격 데이터셋에 한하여 평가되며, 각 기법에 대한 탐지 성능이 공정하게 평가되었는지를 확인하기 위한 평가 프레임워크가 부족한 상황이다. 따라서 본 논문에서는 machine learning/deep learning에 기반하여 제안된 차랑용 IDS 5가지를 선정하고, 기존에 공개된 데이터셋을 이용하여 제안된 기법들에 대한 비교 및 평가를 진행한다. 공격 데이터셋에는 CAN의 대표적인 4가지 공격 유형이 포함되어 있으며, 추가적으로 본 논문에서는 메시지 주기 유형을 활용한 공격 유형을 제안하고 해당 공격에 대한 탐지 성능을 평가한다.

A Study on the Risk Assessment of River Crossing Pipeline in Urban Area (도심지 하천매설배관의 위험성 평가에 관한 연구)

  • Park, Woo-Il;Yoo, Chul-Hee;Shin, Dong-Il;Kim, Tae-Ok;Lee, Hyo-Ryeol
    • Journal of the Korean Institute of Gas
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    • v.24 no.2
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    • pp.22-28
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    • 2020
  • In this study, quantitative risk assessment was carried out for city gas high-pressure pipelines crossing through urban rivers. The risk assessment was performed based on actual city gas properties, traffic volume and population and weather data in the worst case scenario conditions. The results confirmed that the social and individual risks were located in conditionally acceptable areas. This can be judged to be safer considering that the risk mitigation effect of protecting the pipes or installing them in the protective structure at the time of the construction of the river buried pipe is not reflected in the result of the risk assessment. Also, SAFETI v8.22 was used to analyze the effects of wind speed and pasquil stability on the accident damage and dispersion distances caused by radiation. As a result of the risk assessment, the safety of the pipelines has been secured to date, but suggests ways to improve safety by preventing unexpected accidents including river bed changes through periodic inspections and monitoring.

Development of Web based PSI/ISI Information Management System for Virtual Nuclear Power Plant (Web 기반의 가상원전 PSI/ISI 정보관리 시스템 개발)

  • Shin, Jin-Ho;Lee, Bong-Jae;Song, Jae-Ju;Jang, Mun-Jong
    • Proceedings of the KIEE Conference
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    • 2002.07d
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    • pp.2761-2763
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    • 2002
  • 원자력발전소에서는 건설완료 단계에서 기기, 배관 및 각종 지지구조물에 대하여 PSI(Pre-Service Inspection)를 실시하여 시공된 설비의 건전성을 점검하고, 운영중에는 주기적으로 시간의 경과에 따른 취약화 정도를 비과괴검사로 감시 및 평가하는 ISI (In-Service Inspection)를 실시하여 안전성 관련 설비의 건전성을 점검하고 있다. 이 과정에서 방대한 양의 검사데이터가 생산되며 원전 가동년수가 증가함에 따라 검사자원을 체계적으로 관리하고 자동화 할 수 있는 시스템 개발이 필요하게 되었다. 본 논문에서는 PSI/ISI 검사결과 정보관리를 비롯하여 검사 기초자료 관리 및 검사계획 수립, 파괴역학 분식 기능 등을 포함한 Web 기반의 Application 개발 사례를 소개한다. 또한 가상현실 기법을 적용하여 기존의 2차원적 DB 운영을 3차원 가상공간에서 운영할 수 있는 'Touch & Tell' 기법을 개발하고 그 구현방법을 제시한다.

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Security Requirements Analysis on IP Camera via Threat Modeling and Common Criteria (보안위협모델링과 국제공통평가기준을 이용한 IP Camera 보안요구사항 분석)

  • Park, Jisoo;Kim, Seungjoo
    • KIPS Transactions on Computer and Communication Systems
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    • v.6 no.3
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    • pp.121-134
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    • 2017
  • With rapid increasing the development and use of IoT Devices, requirements for safe IoT devices and services such as reliability, security are also increasing. In Security engineering, SDLC (Secure Development Life Cycle) is applied to make the trustworthy system. Secure Development Life Cycle has 4 big steps, Security requirements, Design, Implementation and Operation and each step has own goals and activities. Deriving security requirements, the first step of SDLC, must be accurate and objective because it affect the rest of the SDLC. For accurate and objective security requirements, Threat modeling is used. And the results of the threat modeling can satisfy the completeness of scope of analysis and the traceability of threats. In many countries, academic and IT company, a lot of researches about drawing security requirements systematically are being done. But in domestic, awareness and researches about deriving security requirements systematically are lacking. So in this paper, I described about method and process to drawing security requirements systematically by using threat modeling including DFD, STRIDE, Attack Library and Attack Tree. And also security requirements are described via Common Criteria for delivering objective meaning and broad use of them.

PD Diagnosis of Power Cables for Nuclear Power Plant (원자력발전소 전력케이블 부분방전 진단 사례)

  • Han, Sung-Heum;Joo, Kwang-Ho;Ha, Che-Wung
    • Proceedings of the KIEE Conference
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    • 2011.07a
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    • pp.804.1-805
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    • 2011
  • 1980년대 건설된 국내 원자력발전소는 30년 정도의 운전 년수를 기록하고 있다. 가동연한의 증가에 따라 원자력발전소에 설치되어 있는 전력케이블은 열화진단 및 유지보수의 필요성이 증대되고 있다. 주기적 안전성 평가(Periodic Safety Review) 및 계속운전과 관련하여서도 고압케이블의 관리방안이 지속적으로 요구되고 있다. 본 논문에서는 원자력발전소에 설치되어 있는 13.8kV 고압케이블의 건전성을 확인하기 위하여 국내 최초 원자력발전소 운전 중 부분방전 진단을 수행하였다. 특히 측정장비별 특성 및 신뢰성을 제고하기위하여 Techimp사의 PD-Base I 장비와 OMICRON사 MPD600 장비 두가지를 가지고 케이블 부분방전(Partial Discharge; PD)열화진단을 수행 하였고 결과를 비교하였다.

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