• Proceedings of the Korean Institute of Industrial Safety Conference
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• 2002.05a
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• pp.403-406
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• 2002

가정용 및 산업용으로 사용되고 있는 천연가스는 70kg/cm1의 압력으로 지하에 매설되어 있는 API 5L X65재질의 배관을 통하여 공급되고 있다 생산기지에서 공급되는 압력이 70kg1cmr이지만 가스소비량에 따라 계절별 및 월별 가스 내압이 변화되고 있다. 하루에도 최대 2회정도 주기적으로 변화를 보이고 있다. 본 연구에서는 API 5L X65등급의 가스배관 모재 및 용접부에 일정한 형태의 가우지 결함을 가공하여 현재 사용중인 내압 조건과 유사한 내압변화를 재현하여 피로수명을 평가하였다.(중략)

• Transactions of the Korean Society of Mechanical Engineers A
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• v.39 no.1
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• pp.11-17
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• 2015

High-density polyethylene (HDPE) piping, which has recently been applied to safety class III piping in nuclear power plants, can be butt-joined through the thermal fusion process, which heats two fused surfaces and then subject to axial pressure. The thermal fusion process generates bead shapes on the butt fusion. The stress concentrations caused by the bead shapes may reduce the fatigue lifetime. Thus, investigating the effect of the thermal butt fusion beads on fatigue behavior is necessary. This study examined the fatigue behavior of thermal butt fusion via a tensile fatigue test under stress-controlled conditions using finite element elastic stress analysis. Based on the results, the presence of thermal butt fusion beads was confirmed to reduce the fatigue lifetime in the low-cycle fatigue region while having a negligible effect in the medium- and high-cycle fatigue regions.

• Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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• 1995.04a
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• pp.318-321
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• 1995

원자력 발전소의 안전성 보장 및 신뢰성 향상을 위하여 시운전 단계에서 원자력 발전소내 안전등급에 해당하는 배관계통의 상태 확인을 위하여 각종시험을 하도록 되어있다. 특히 새로운 설계기념, 크기 또는 용량을 갖는 원자로 모델에 대해서는 필수적으로 건전성 평가를 하게 되었다. 이를 위해 발전소 건설기간에 시행하는 고온 기능시험 중에 원자로 주변 주요 시스템인 원자로 냉각재 루프 계통에 대한 건전성 확인을 위해 압전형 고온 가속도 센서를 이용하여 정상운전상태의 진동을 측정하여 시스템 진동거동을 규명하였다. 배관시스템의 일상운전상태는 유체의 흐름과 기기운전이 일정한 정상상태와 펌프의 기동 또는 정지 및 밸브의 급격한 개폐등으로 발생하는 과도상태로 나눌 수 있다. 따라서 두 가지 상태의 진동을 측정해야 한다. 배관계통은 정상운전 상태로 설계수명을 유지할 수 있어야 하므로 정상진도잉 최소화 되어야 한다. 진동 평가기준은 배관재질의 응력(S/N 커브) 곡선을 참조하여 설계수명내에 손상이 일어나지 않도록 재료의 허용응력을 산정하고 이를 진동변위로 환산하여 정한 것이며 이 값에 측정 데이타를 비교하여 1차계통 배관의 건전성을 확인하였다.

• Proceedings of the KSME Conference
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• 2001.06a
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• pp.316-321
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• 2001

A previous feasibility study for the Korean lead plant, PLiM Phase I, showed a strong possibility of continued operation beyond the original licensed period. In 1998, PLiM Phase II study was initiated aimed at performing additional detailed evaluations on a wider range of components. The objective of this paper is to present the Korean PLiM efforts for Class 1 piping which is identified as one of the critical components with regard to long-term operation. The key findings such as typical design features, degradation mechanisms, technical issues, draft results from the lifetime evaluation for Class 1 piping of the lead plant are briefly described.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.13 no.2
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• pp.1-18
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• 2017

Metal fatigue is an important aging mechanism that material characteristics can be deteriorated when even a small load is applied repeatedly. An accurate fatigue evaluation is very important for component structural integrity and reliability. In the design stage of a nuclear power plant, the fatigue evaluations of the Class 1 components have to be performed. However, operating experience shows that the design evaluation can be very conservative due to conservatism in the transient severity and number of occurrence. Therefore, the fatigue monitoring system has been considered as a practical mean to ensure safe operation of the nuclear power plants. The fatigue monitoring system can quantify accumulated fatigue damage up to date for various plant conditions. The purpose of this paper is to describe the fatigue monitoring procedure and to introduce the fatigue monitoring program developed by the authors. The feasibility of the fatigue monitoring program is demonstrated by comparing with the actual operating data and finite element analysis results.

• Transactions of the Korean Society of Mechanical Engineers A
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• v.39 no.4
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• pp.405-413
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• 2015

In the US, the number of cases of subterranean water contamination from tritium leaking through a damaged buried nuclear power plant pipe continues to increase, and the degradation of the buried metal piping is emerging as a major issue. A pipe blocked from corrosion and/or degradation can lead to loss of cooling capacity in safety-related piping resulting in critical issues related to the safety and integrity of nuclear power plant operation. The ASME Boiler and Pressure Vessel Codes Committee (BPVC) has recently approved Code Case N-755 that describes the requirements for the use of polyethylene (PE) pipe for the construction of Section III, Division 1 Class 3 buried piping systems for service water applications in nuclear power plants. This paper contains tensile and slow crack growth (SCG) test results for high-density polyethylene (HDPE) pipe welds under the environmental conditions of a nuclear power plant. Based on these tests, the fracture surface of the PENT specimen was analyzed, and the fracture mechanisms of each fracture area were determined. Finally, by using 3D finite element analysis, limit loads of HDPE related to premature failure were verified.

• Journal of the Korean Institute of Gas
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• v.7 no.1 s.18
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• pp.33-40
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• 2003

In this work, a novel approach was introduced to assess cost of loss resulting from risk as well as to help deciding inspection period through quantifying risk. In order to quantifying risk of city gas pipeline, frequency and consequence analysis were required. The main causes of city gas accident were analyzed to be digging, external corrosion, ground movement, and equipment failure. Tools to evaluate frequency of each cause was also suggested. Among city gas accidents, fire damage is the dominant one and mainly discussed; fatality, burning injury, and damage to building were estimated using the consequence model suggested. By combining frequency and consequence analysis, evaluating cost of risk management together with calculating example. This work could be applicable for city gas companies to plan how to manage risk most effectively.