• 제목/요약/키워드: integrity assessment

검색결과 554건 처리시간 0.031초

철도시스템 안전무결성레벨(SIL)의 검증방안에 대한 연구 (A Study on the Verification Method for Railway System SIL)

  • 박영수
    • 한국철도학회:학술대회논문집
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    • 한국철도학회 2007년도 춘계학술대회 논문집
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    • pp.936-940
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    • 2007
  • This paper is about the study on the verification method for railway system SIL which is frequency of hazard, composing Risk, one of the measurement standards for railway system safety. Frequency of hazard can be identified by using FMECA, or HAZOP, and the assessment of identified dangerous failure rate should be done by systematic methods such as FTA. Therefore, this paper provides the hazard identification level for SIL verification and the requirements necessary to verify the integrity of analysis activity.

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전방십자인대 손상의 자기공명영상 (Magnetic Resonance Imaging of ACL Injury)

  • 송은규
    • 대한관절경학회지
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    • 제1권1호
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    • pp.31-35
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    • 1997
  • MRI(magnetic resonance imaging) is very useful to visualize the anterior cruciate ligament (ACL) injury of the knee. Differential features of ACL injury at MRI according to acute and chronic stage should be evaluated to enable accurate assessment of the integrity or ACL. Distinguishing features of normal anatomy. acute and chronic injuries or ACL at MRI will be reviewed.

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Deterministic Fracture Mechanics Analysis of Pressurized Thermal Shock

  • M. J. Jhung;Park, Y. W.
    • Nuclear Engineering and Technology
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    • 제30권5호
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    • pp.470-484
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    • 1998
  • An analysis program for the evaluation of pressure vessel integrity under pressurized thermal shock (PTS) is developed. For given material properties and transient history such as temperature and pressure, the stress distribution is calculated and then stress intensity factors are obtained for a wide range of crack sizes. The stress intensity factors are compared with the fracture toughness to check if cracking is expected to occur during the transient. Using this program a round robin problem of PTS during a small break loss of coolant transient has been analyzed as a part of the international comparative assessment study. The allowable maximum reference nil-ductility transition temperatures are determined for various crack sizes.

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철도신호시스템의 정량적 분석 기법을 통한 SIL 도출방안 검토 (Quantitative analysis to derive SIL in the railway signalling system)

  • 정의진;김양모
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 2003년도 하계학술대회 논문집 B
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    • pp.1303-1305
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    • 2003
  • It is very important to ensure system safety during the process of developing a system. Railway system is also devoting a great portion for the safety. Nowadays many countries leading railway industry have their own system assessment principles according to the situation of their train control systems. In this paper, several principles to derive Safety Integrity Level (SIL) are represented in the railway signalling system. The characteristics of those principles are also considered respectively.

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Rock Permeability Estimation from Hydraulic Injection Tests in a Sealed Borehole Interval

  • Quach, Nghiep Q.;Jo, Yeonguk;Chang, Chandong
    • 지질공학
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    • 제28권1호
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    • pp.1-9
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    • 2018
  • We propose a borehole test technique to estimate permeability of rocks in borehole. The borehole tests are hydraulic injection tests such as leak-off test and hydraulic fracturing tests, which are originally conducted for stress or casing integrity assessment and not for permeability measurement. We use one-dimensional radial diffusion equation to interpret fluid injection test results in terms of permeability. We apply this technique to a leak-off test conducted at a depth of 700 m in a wellbore, where rock formation is mudstone. The estimated permeability is at an order of $10^{-16}m^2$, which is somewhat high but within the range reported for mudstones previously. Quantitative rick assessment suggests that an accurate measurement of open hole section length is important to improve reliability of results. More data may be needed to ensure the reliability of this technique. If validated, however, this technique can provide cost-effective estimation of in situ permeability without conducting independent permeability tests in borehole.

결함 평가에서 용접 잔류응력 분포의 영향 (Effect of Residual Stress Distributions in Defect Assessment)

  • 이세환;이형연;김종범;이재한
    • 대한용접접합학회:학술대회논문집
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    • 대한용접접합학회 2006년 추계학술발표대회 개요집
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    • pp.15-17
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    • 2006
  • Weld residual stresses can be a major concern in structural integrity assessments such as a nuclear power plant. In this paper, detailed weld residual stress analyses were presented for a typical multi-pass weld of pipe-butt weld and plate T-butt weld. The calculated residual stress distributions were compared with those of the measured data and recommended profiles in R6 and BS7910. Defect assessment which is based on the stress intensity factor(SIF) calculations was carried out for a plate T-butt weld with cracks considering the weld residual stress distributions.

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A Safety Assessment Methodology for a Digital Reactor Protection System

  • Lee Dong-Young;Choi Jong-Gyun;Lyou Joon
    • International Journal of Control, Automation, and Systems
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    • 제4권1호
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    • pp.105-112
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    • 2006
  • The main function of a reactor protection system is to maintain the reactor core integrity and the reactor coolant system pressure boundary. Generally, the reactor protection system adopts the 2-out-of-m redundant architecture to assure a reliable operation. This paper describes the safety assessment of a digital reactor protection system using the fault tree analysis technique. The fault tree technique can be expressed in terms of combinations of the basic event failures such as the random hardware failures, common cause failures, operator errors, and the fault tolerance mechanisms implemented in the reactor protection system. In this paper, a prediction method of the hardware failure rate is suggested for a digital reactor protection system, and applied to the reactor protection system being developed in Korea to identify design weak points from a safety point of view.

APR1400 원자로내부구조물 종합진동평가 측정위치 선정 기준 (Selection Criteria of Measurement Locations for Advanced Power Reactor 1400 Reactor Vessel Internals Comprehensive Vibration Assessment Program)

  • 고도영;김규형;김성환
    • 한국소음진동공학회논문집
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    • 제21권8호
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    • pp.708-713
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    • 2011
  • U.S. nuclear regulatory commission(NRC) regulatory guide(RG) 1.20 requires a comprehensive vibration assessment program(CVAP) for use in verifying the structural integrity of reactor vessel internals(RVI) for flow-induced vibrations prior to commercial operation. The CVAP program consist of vibration and fatigue analysis, a vibration measurement program, an inspection program, and a correlation of their results. One of the main purposes of the analysis program is to select measurement locations, however measurement locations can not be determined by only analysis results, therefore we developed selection criteria of measurement locations for advanced power reactor 1400(APR1400) RVI CVAP, It will be used to select measurement locations and instrument types for APR1400 RVI CVAP.

열차제어시스템의 안전계획 수립에 관한 연구 (A Study on the Safety Plan for a Train Control System)

  • 김종기;신덕호;이기서
    • 한국철도학회논문집
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    • 제9권3호
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    • pp.264-270
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    • 2006
  • In this paper we present a safety plan to be applied to the development of the TCS(Train Control System). The safety plan that can be applied to the life cycle of a system, from the conceptual design to the dismantlement, shows the whole process of the paper work in detail through the establishment of a goal, analysis and assessment, the verification. In this paper we study about the making a plan, the preliminary hazard analysis, the hazard identification and analysis to guarantee the safety of the TCS. The process far the verification of the system safety is divided into several steps based on the target system and the approaching method. The guarantee of the system safety and the improvement of the system reliability is fellowed by the recommendation of the international standards.