• 국제학술발표논문집
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• The 5th International Conference on Construction Engineering and Project Management
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• pp.352-358
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• 2013

As amount of information in construction industry is growing, the role of information system in project management is becoming increasingly important. With the emerging IT application to the advancing construction industry, construction project management system with advanced technology has been progressed vigorously to improve construction productivity and management efficiency. Recently, a web-based Project Management Information System (PMIS) is developed to support decision-making process by efficiently managing project related information generated from various discipline. Many firms are in the process of developing the PMIS system or already have been applied the system to various projects. However, PMIS is still in its early stage of development to be applied at industrial plant construction projects that process management is significantly emphasized for the successful execution of the project. With the complexity of the industrial plant projects, the industry practitioners need to be able to visualize the construction schedule information to manage the project efficiently. This study suggests methodologies for improving PMIS specialized for industrial plant piping construction projects to estimate the baseline schedule and performance measurement more accurately by developing a framework for the piping construction projects. By using this developed system, the researchers expect that piping construction projects will be more efficiently managed on a real-time basis through measuring progress of piping at each and every state of progress milestone and provide management with opportunities to forecast the level of efforts required to execute the remaining work scope in a timely manner

• 한국항해항만학회지
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• 제45권4호
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• pp.212-223
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• 2021

본 논문에서는 해양구조물의 배관에 작용하는 환경조건과 구조물의 움직임에 따른 구조안전성 평가를 수행하였다. 배관에 작용하는 조건은 N₂ generator의 설계 조건을 분석하여 최고온도와 최저온도 조건을 적용하였다. 구조물의 움직임은 DNV 규칙에 따라 계산하여 적용하였다. 각각의 조건을 조합하고 열 하중, 운동 하중 그리고 배관지지대의 유무에 따라 총 26가지 하중 조합을 구성하였고 상용프로그램인 MSC Patran/Nastran을 이용하여 해석을 진행하였다. 열해석은 Steady-state 방법인 Sol 153, 열-구조 연성 해석은 Linear-static 방법인 Sol 101을 각각 적용하여 수행하였다. 해석 결과, Set 1과 Set 2에서는 배관 내의 온도가 낮을수록, Set 3에서는 온도가 높을수록, Set 4에서는 배관 내외부의 온도 차가 클수록 응력이 증가하는 경향이 있었다. 하지만, 온도 하중만 있는 조건과 운동 하중만 있는 조건에서의 응력의 합이 두 하중의 복합 하중 조건에서의 응력과 같은 값을 나타내지는 않았다. 즉, 운동 하중에 의한 영향은 운동의 방향, 배관의 배치나 지지대의 위치 등에 따라 달라진다는 것을 알 수 있다. 따라서, 설계 시점에서 배관에 작용하는 운동 하중의 크기와 방향, 배관의 배치 그리고 배관 지지대의 위치 등을 종합적으로 고려할 필요가 있다.

• 한국정밀공학회지
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• 제17권4호
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• pp.233-239
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• 2000

Investigation results are presented fur the shaft end displacements due to the elastic deformation of the casing and support in double suction centrifugal pump. Suction and discharge nozzles of the pump are subject to external piping loads and, in API 610, maximum values of their components are specified. This means that each nozzle can be subject to various combinations of loading conditions. Considering upper and lower criteria of each load, we must perform for the 4,096 load cases, and assign the direction and range of the loads. So, this paper develops an efficient procedure(Compliance Coefficient Method) to calculate the shaft end displacements(＠ coupling) to determine whether satisfying the pump's standard. Also, we analyzed the effects of the casing and support thickness on shaft end displacements.

• 한국압력기기공학회 논문집
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• 제8권2호
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• pp.33-41
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• 2012

The component cooling water heat exchangers are critical components in a nuclear power plant. As the operation years of the heat exchanger go by, the maintenance costs required for continuous operation also increase. Most heat exchangers have carbon steel shells, tube support plates and flow baffles. The titanium tube is susceptible to flow induced vibration. The damage on carbon steel tube support rod and titanium tube around cooling water entrance area is inevitable. Therefore, analysis of internal flow around the component cooling water entrance and tube channel is a good opportunity to seek for failure prevention practice and maintenance method. The numerical study was carried out by FLUENT code to find out the causes of tube failure and its location.

• 한국압력기기공학회 논문집
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• 제6권2호
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• pp.16-19
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• 2010

In this study, the axial ODSCC occurrence of domestic OPR 1000 steam generator tube was caused by the tube weakness and the sludge accumulation in the secondary side of steam generator. Inconel 600 HTMA used as tube material is related to most of tube leakage accidents in the world and also these ODSCCs were detected mainly at the 5th TSP(Tube Support Plate) to the 8th TSP of hot leg side. These elevations(5th TSP to 8th TSP) pave the way for the sludge accumulation. As a result of EC(Eddy Current) Bobbin and RPC data analysis, ODSCCs were occurred at contact points of tube and tube support plate. The more accumulated sludge, the higher occurrence frequency of ODSCC.

• 한국압력기기공학회 논문집
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• 제14권2호
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• pp.16-23
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• 2018

In order to investigate the ways to enhance the seismic performance of APR1400 seismic fragile equipment by direct design changes, four equipment such as Reactor Vessel Support, Integrated Head Assembly, Remote Shutdown Console, and Pressurizer are reviewed using information of the main dimensions, seismic stress evaluation results, design FRS, etc. in this paper. In addition to the direct reinforcement of equipments, the feasibility of seismic isolation for the safety related cabinet is also investigated and the actual adaption plan of a commercial spring-damper system is briefly reviewed.

• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2013년도 추계학술대회 논문집
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• pp.699-705
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• 2013

This paper presents vibration testing, control, and finite element analysis of a piping system, which is subjected to the changes in fluid levels. Nuclear power plants typically employ a cooling system that uses sea water. These systems are subjected to dynamic characteristic changes caused by sea-level variations, which introduces failures of cooling system components. Therefore in this study, analytical and experimental studies were performed to understand the effect of sea-level changes on the dynamic characteristics of piping systems. It was shown that, as the sea-level increases, pipe's natural frequencies decreases in relation to its mode shape. A 1/14 scale model was also built to compare the results obtained by the analytical study. A good agreement between experiment and analytical studies were observed. Finally, an on-line resonant frequency identification system was proposed and developed, which utilizes piezoelectric transducers as sensors and actuators, in order to avoid catastrophic failure of piping systems.

• Nuclear Engineering and Technology
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• 제56권5호
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• pp.1627-1637
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• 2024

This research paper proposes a novel methodology for predicting the optimal location of friction supports to effectively mitigate vibrational energy in piping systems. The incorporation of friction forces in the dynamic characteristics of the system introduces inherent nonlinearity, making its analysis challenging. Typically, numerical solutions in the time domain are employed to circumvent the complexities associated with finding analytic solutions for nonlinear systems. However, time domain analysis (TDA) can be computationally intensive and demand significant computational resources due to the intricate calculations stemming from nonlinearity. To address this computational burden, this study presents an efficient approach based on linear analysis to predict the ideal position for installing friction supports as a replacement for fixed supports. Furthermore, we investigate the relationship between the installation positions of friction supports and their effectiveness in absorbing vibrations using the harmonic balanced method (HBM). Both methodologies are validated by comparing the obtained results with those obtained through time domain analysis (TDA) using the finite element method (FEM).

• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 1990년도 추계학술대회논문집; 한양대학교, 서울; 24 Nov. 1990
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• pp.113-124
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• 1990

Tap lines are small branch piping generally less than two inches in diameter. They typically branch off of header piping having a much larger diameter. An example of a common tap line is a 3/4 inch size high point vent or low point drain. Most tap lines have at least one valve near the header tap connection to provide isolation. Two valves are often required for double isolation. A light water reactor(LWR) nuclear power plant will have several hundred tap lines. These lines come in many sizes and shapes and serve numerous functions. A single process piping valve may have three different tap lines associated with it (figure 1). Table 1 delineates the different categories of tap lines. Vibration failures of tap lines are a common occurrence in all industrial plants including nuclear and fossil power plants. These types of failures constitute a significant percentage of all piping related failures. An unscheduled plant shutdown or outage resulting from the failure of a tap line decreases plant reliability and may have a detrimental effect on plant safety. Most tap line vibration failures can be avoided through the use of appropriate routing and support techniques. Standardized designs can be developed for use in a myriad of applications. These designs will not only minimize failures but will also reduce the necessary analysis and installation efforts.

• 한국유체기계학회 논문집
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• 제7권1호
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• pp.30-35
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• 2004

The HANARO, a multi-purpose research reactor of 30 MWth open-tank-in-pool type, has been under normal operation since its initial criticality in February, 1995. Many experiments should be safely performed to activate the utilization of the HANARO. HANARO flow simulation facility is being developed for the endurance test of reactivity control units for extended life time and the verification of structural integrity of those experimental equipments prior to loading in the HANARO. This facility is composed of three major parts; a half-core structure assembly, a flow circulation system and a support system. The flow circulation system is composed of a circulation pump, a core flow piping, a core bypass flow piping and instruments. The system is to be filled with de-mineralized water and the flow should be met the design requirements to simulate a similar flow characteristics in the core channel of the half-core structure assembly to the HANARO. This paper, therefore, presents an analytical analysis to study the flow behavior of the system. Computational flow analysis has been performed for the verification of system pressure variation through the three-dimensional analysis program with the standard $k-{\epsilon}$ turbulence model and for the verification of the structural piping integrity through the finite element method. According to the analysis results, it could be said that the design requirements and the structural piping integrity of the flow circulation system are satisfied.