• Structural Engineering and Mechanics
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• 제72권1호
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• pp.31-41
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• 2019

Structural integrity assessment of piping components is of paramount important for remaining life prediction, residual strength evaluation and for in-service inspection planning. For accurate prediction of these, a reliable fracture parameter is essential. One of the fracture parameters is stress intensity factor (SIF), which is generally preferred for high strength materials, can be evaluated by using linear elastic fracture mechanics principles. To employ available analytical and numerical procedures for fracture analysis of piping components, it takes considerable amount of time and effort. In view of this, an alternative approach to analytical and finite element analysis, a model based on relevance vector machine (RVM) is developed to predict SIF of part through crack of a piping component under fatigue loading. RVM is based on probabilistic approach and regression and it is established based on Bayesian formulation of a linear model with an appropriate prior that results in a sparse representation. Model for SIF prediction is developed by using MATLAB software wherein 70% of the data has been used for the development of RVM model and rest of the data is used for validation. The predicted SIF is found to be in good agreement with the corresponding analytical solution, and can be used for damage tolerant analysis of structural components.

• 한국공작기계학회:학술대회논문집
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• 한국공작기계학회 2003년도 춘계학술대회 논문집
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• pp.73-78
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• 2003

Ultrasonic measurement is one of important technologies in the lift-time maintenance of nuclear poler plant. Ultrasonic inspection system is consisted of the operator, equipment and procedure. The reliability of ultrasonic inspection system is affected by its ability. The performance demonstration round robin was conducted to quantify the capability of ultrasonic inspection for in-service. The small number of teams who employed procedures that met or exceeded ASME Sec. XI Code requirements detected the piping of nuclear power plant with various cracks to evaluate the capability of detection and sizing. In this paper, the statistical reliability assessment of ultrasonic nondestructive inspection data using Monte Carlo simulation is presented. The results of the probability of detection (POD) analysis using Monte Carlo simulation are compared to these of logistic probability model. In these results, Monte Carlo simulation was found to be very useful to the reliability assessment f3r the small hit/miss data sets.

• 대한용접접합학회:학술대회논문집
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• 대한용접접합학회 2004년도 춘계 학술발표대회 개요집
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• pp.118-120
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• 2004

The non-destructive examinations for Yonggwang unit 6 was conducted in four different fields, these are 1)all non-destructive inspections for components, piping weldments and structures, 2)automated ultrasonic inspection for pressure vessels weldments. As the results, there were no big indications, and all indications detected during inspection were evaluated as the metallurgical and geometrical non-reinvent indications form weldments. Especially for the weldment of pipes, PD(Performance Demonstration) was applied as a UT inspection method according to 1995 edition of ASME code Sex. XI, this resulted in improvement of the reliability of UT inspection.

• 한국압력기기공학회 논문집
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• 제16권2호
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• pp.1-9
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• 2020

Large-scale industrial facility structures continue to deteriorate due to the effects of operating and environmental conditions. The problems of these industrial facilities are potentially causing economic losses, environmental pollution, casualties, and national losses. Accordingly, in order to prevent disaster accidents of large structures in advance, the necessity of diagnosing structures using non-destructive inspection techniques is being highlighted. The defect occurrence, location and defect type of the structure are important parameters for predicting the remaining life of the structure, so continuous defect observation is very important. Recently, many researchers have been actively researching real-time monitoring technology to solve these problems. Structure Health Monitoring Inspection is a technology that can identify and respond to the occurrence of defects in real time, but there is a limit to check the degree of defects and the direction of growth of defects. In order to compensate for the shortcomings of these technologies, the importance of defect imaging techniques is emerging, and in order to find defects in large structures, a method of inspecting a wide range using guided ultrasonic is effective. The work presented here introduces a calculation for the shape factor for evaluation of the damaged area, as well as a variable β parameter technique to correct a damaged shape. Also, we perform research in modeling simulation and an experiment for comparison with a suggested inspection method and verify its validity. The curved structure image obtained by the advanced RAPID algorithm showed a good match between the defect area and the shape.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 추계학술발표회
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• pp.717-718
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• 2005

• 한국압력기기공학회 논문집
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• 제9권1호
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• pp.62-69
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• 2013

A probabilistic assessment code, PRO-LOCA ver. 3.7 which was developed in an international co-operative research program, PARTRIDGE was evaluated by conducting sensitivity analysis. The effect of some variables such as simulation methods (adaptive sampling, iteration numbers, weld residual stress model), crack features(Poisson's arrival rate, maximum numbers of cracks, initial flaw size, fabrication flaws), operating and loading conditions(temperature, primary bending stress, earthquake strength and frequency), and inspection model(inspection intervals, detectable leak rate) on the failure probabilities of a surge line nozzle was investigated. The results of sensitivity analysis shows the remaining problems of the PRO-LOCA code such as the instability of adaptive sampling and unexpected trend of failure probabilities at an early stage.

• 한국압력기기공학회 논문집
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• 제12권1호
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• pp.115-125
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• 2016

The prototype SFR has currently been under design by KAERI. The size of its major components is much larger than that of APR1400 and high temperature materials are applied for it. The increased size of components and those specific materials effect on material procurement, manufacturing process and fabrication facilities. The manufacturing methods are studied for Reactor Vessel/Guard Vessel, Control Rod Drive Mechanism, Heat Exchanger, Primary Pump, Reactor Vessel Internals, Steam Generator and In-Vessel Transfer Machine. The proper manufacturing methods are suggested for each component including side forging technology for ultra large forgings of Reactor Vessel to minimize the weld seams on which In-service Inspection should be conducted.

• 한국압력기기공학회 논문집
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• 제16권2호
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• pp.18-24
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• 2020

When a damage occurs in the nuclear fuel burning in the reactor, fission products that should be in the nuclear fuel rod are released into the reactor coolant. In this case, sipping test, a series of non-destructive inspection methods, are used to find leakage in nuclear fuel assemblies during the power plant overhaul period. In addition, the sipping test is also used to check the integrity of the spent fuel for moving to an intermediate dry storage, which is carried out as the first step of nuclear decommissioning, . In this paper, the principle and characteristics of the sipping test are described. The structure of the sipping inspection equipment is largely divided into a suction device that collects fissile material emitted from a damaged assembly and an analysis device that analyzes their nuclides. In order to make good use of the sipping technology, the radioactive level behavior of the primary system coolant and major damage mechanisms in the event of nuclear fuel damage are also introduced. This will be a reference for selecting an appropriate sipping method when dismantling a nuclear power plant in the future.

• 한국화재소방학회논문지
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• 제29권3호
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• pp.21-30
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• 2015

본 연구는 스프링클러설비용 CPVC관과 신축배관 접속부분에서의 누수저감을 위하여 신축배관을 연결하기 위한 밸브소켓과 신축배관 너트부분에 삽입되는 수밀 고무패킹 재질에 대한 국내 및 국외 관련 규격의 검토와 관련 시험 등을 통해 대책을 제안하고자 한다. 누수시험을 통해 밸브소켓 재질은 신축배관 너트부분이 금속제인 경우 금속제로 사용하거나 신축배관 너트부분의 재질을 합성수지제로 사용하여야함을 알 수 있었다. 또한 밸브소켓의 적정 품질 확보를 위해서는 나사산 규격과 검사기준으로 KS B 0221(관용평행나사)와 나사산 검사규격을 KS B 5223(관용 평행나사 게이지)에 따르도록 관련 기준을 개정할 필요가 있다. 그리고 신축배관 너트부분에 설치되는 수밀용 고무링 소재에 대해 세부적인 기준이 없어 NBR과 EPDM 소재가 함께 사용되고 있으나 수밀성이 우수한 EPDM 소재가 사용되도록 관련 기준을 개정할 필요가 있다.

• 비파괴검사학회지
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• 제30권4호
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• pp.317-323
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• 2010

원자력발전소 배관 용접부에 대한 수동 초음파검사는 KPD(Korean Performance Demonstration)의 일반 절차서를 사용하여 기량 검증을 인정받고 있으나, 자동 초음파검사의 경우에는 일반 절차서가 없으며 해당 자동 검사 장비를 이용하여 절차서 기량 검증을 받아야 한다. 현재까지 국내에서 수행되고 있는 자동 초음파검사에 대한 절차서 기량검증은 대부분 펄스-반사기법을 적용한 절차서이나, 최근에 각광받고 있는 위상배열 초음파검사 기법을 이용한 절차서 기량검증은 국내에서 시행된 사례가 전무하다. 본 연구에서는 원자력발전소 가동중검사에 위상배열 초음파검사 기법을 적용하기 위하여 위상배열 초음파 신호취득 및 평가 소프트웨어를 개발하고 위상배열 초음파 탐촉자 및 웨지를 설계 하였다. 개발된 절차서에 대하여 결함 검출, 길이 및 크기 측정에 대한 기량검증을 수행하였으며, 검증된 위상배열 초음파탐상검사 절차서는 향후 원자력발전소 배관 용접부 검사에 적용할 예정이다.