• Fire Science and Engineering
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• v.27 no.5
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• pp.26-31
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• 2013

In nuclear power plant, anchor bolts for pressurizer supports are sufficiently used in terms of safety reason, but field inspections have reported that some bolts exceed the limit of their allowable hardness. Because the high level of hardness may lead to failures due to the stress corrosion or fracture toughness, a regular inspection is required for the bolts in nuclear power plant. Thus, this research measures the hardness of bolts currently used in pressurizer supports and then estimates maximum allowable stresses preventing failures by stress corrosion and fracture toughness. Using the ANSYS program, the stresses of the bolts in the regular condition and accidental condition have been calculated, and the possible maximum stress has been compared with the estimated allowable stresses. From the results, the stresses of bolts in the accidental condition satisfy the allowable safety stress from the stress corrosion failure. However, in the future, it shall be needed to consider the reflection of the structure assembling method on the assembling procedure to ensure the pressurizer integrity during maintenance period time.

• Journal of the Korea institute for structural maintenance and inspection
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• v.22 no.6
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• pp.148-156
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• 2018

The integrity assessment of the bridge behavior is generalized by field data of a static load-deformation curve and dynamic properties such as impact factors and natural frequencies. Evaluating it with numerical analysis is a reasonable method. The results of the mockup test and the numerical analysis are corresponded with each other since the behavior of service load proceeds in elastic region. In case of the dynamic behavior of structure, especially for the analysis of vibration, the result of the mockup test differs from the result of numerical analysis a little due to the geometric shape and non-homogeneous materials. In order to converge on these tolerances, this study suggested several numerical models, analyzed the sensitivity and finally offered a practical modeling method for the estimation of bridge on the basis of the result of mockup test. Based on the model substituted concrete section for strands section, the natural frequency of the model composed with axial stiffness of strands or the model applied the modified modulus of elasticity was closest with the result of the mockup test.

• Journal of the Korean Society for Nondestructive Testing
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• v.36 no.4
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• pp.281-287
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• 2016

Fiber Bragg grating (FBG) sensors are applied in structural health monitoring (SHM) in various application fields because of their ease of multiplexing and capability of performing absolute measurements. Moreover, the packaging methods of FBG sensors accelerate their commercialization rapidly. However, long-term SHM exposes the FBG sensors to cyclic thermal loads, and a investigation is required because it finally leads to the signal instability of the FBG sensors. In this study, the effects of sensor packaging methods two methods are generally used for the FBGs: (bonding both sides of the FBG or bonding the FBG directly on signal stability of FBG sensors are investigated. Tests are conducted on specimens in a thermal chamber, over a temperature range from $-20^{\circ}C$ to $60^{\circ}C$ for 300 cycles. Signal characteristics such as Bragg wavelength, light intensity and full width at half maximum are examined and are compared with those of the FBG sensors, obtained in a previous study under direct bonding conditions. From the comparison, it is observed that the FBG sensors with bonding on both sides of the FBG demonstrate higher signal stabilities when exposed to cyclic thermal loads during long-term SHM. Consequently, it guarantees more effectiveness when packaging the FBG sensors.

• Journal of the Korean Society for Railway
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• v.17 no.4
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• pp.260-269
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• 2014

Transition tracks are an alternative for enhancing the long-term serviceability and durability of concrete track components in railway bridges. The goal of this paper is to investigate the structural behavior for transition track systems of railway bridge deck ends. In this study, the structural behavior of transition tracks such as the variations in static, dynamic, and fatigue behaviors and dynamic properties (natural frequency and damping ratio) are assessed and compared through performing loading tests and finite element analyses using actual vehicle impact loadings. As a result, it is found that the structural behavior of the transition track system is expected to satisfy the actual vehicle impact loading, and the variation in the neutral axis and dynamic characteristics are not affected by the fatigue loading. Therefore, it is inferred that the structural capacity and long-term durability of the transition track system is proven.

• Journal of the Computational Structural Engineering Institute of Korea
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• v.17 no.4
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• pp.405-412
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• 2004

During the irradiation tests of material and fuel rod, all components of the cylindrical structure with multiple holes act like heat sources due to high gamma heat and fission heat. The objective of this study is to formulate the general solution for the temperature distribution to estimate the thermal integrity of structure during irradiation tests. For the temperature distribution analysis, the two-dimensional heat conduction theory is used. The unmerical analysis is performed by the commercial finite element analysis code, ANSYS 6.1. If the cylindrical structure with hole number would not exceed three holes, the analysis results and finite element results are good agreement together. For the structure with four holes, the discrepancy between FE results and analysis results of the structural temperature distribution is increased.

• Journal of Korean Tunnelling and Underground Space Association
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• v.25 no.6
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• pp.509-523
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• 2023

The high-level nuclear waste (HLW) repository is exposed to complex environmental conditions consisting of high temperature, high humidity, and radiation, resulting in structural deterioration. Therefore, structural health monitoring is essential, and piezo sensors are used to detect cracks and estimate strength. However, since the monitoring sensors installed in the disposal tunnel and disposal container cannot be replaced or removed, the quantitative life of the monitoring sensor and its suitability must be assessed. In this study, the life of a piezo sensor for monitoring was assessed using an accelerated life test (ALT). The failure mode and mechanism of the piezo sensor under high temperature conditions were determined, and temperature stress's influence on the piezo sensor's life was analyzed. ALT was conducted on temperature stress and the relationship between temperature stress and piezo sensor life was suggested. The life of the piezo sensor was assessed using the Weibull probability distribution and the Arrhenius acceleration model. The suggested relationship can be used in multiple stress ALT designs for more precise life assessment.

• Journal of the Korea institute for structural maintenance and inspection
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• v.26 no.4
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• pp.30-39
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• 2022

Maintaining structural integrity of major apparatuses in a nuclear power plant, including piping system, is recognized as a critical safety issue. The integrity of piping system is also a critical matter related to the safety of a nuclear power plant. The actual failure mode of a piping system due to a seismic load is the leakage due to a fatigue crack, and the structural damage mechanism is the low-cycle fatigue due to large relative displacement that may cause plastic deformation. In this study, in-plane cyclic loading tests were conducted under various constant amplitudes using specimens composed of steel straight pipes and a steel pipe tee in the piping system of a nuclear power plant. The loading amplitude was increased to consider the relative displacement generated in the piping system under seismic loads, and the test was conducted until leakage, which is the limit state of the steel pipe tee, occurred due to fatigue cracks. The limit state of the steel pipe tee was expressed using a damage model based on the damage index that used the force-displacement relationship. As a result, it was confirmed that the limit state of the steel pipe tee can be quantitatively expressed using the damage index.

• Proceedings of the Korean Vacuum Society Conference
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• 2010.02a
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• pp.273-273
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• 2010

고열부하 환경에 노출되는 핵융합로의 플라즈마 대향부품은 주로 낮은 원자번호 물질-열전도가 좋은 물질-구조체의 순으로 다층 구조를 이루고 있으며, 이들 간의 우수한 접합성은 부품의 성능을 좌우하는 핵심 요소이다. 이러한 플라즈마 대향부품의 건전성을 평가하기 위해서는 고열속의 열부하를 반복적으로 인가하는 시험이 요구되며, 이를 위해 본 연구원에서는 KoHLT-1, 2의 시험시설을 운용하고 있다. 본 시설에서는 열부하원으로서 그라파이터 히터를 사용하며, 히터는 두 개의 시험 대상부품 사이에 설치되고, 히터에 고전류를 인가하여 복사열에 의해 시험 부품에 열부하를 가하게 된다. 고열부하 환경에서 열피로 시험을 위해 히터에 인가되는 전류를 시간에 따라 일정한 패턴으로 반복적으로 ON-OFF 하게 된다. 본 논문에서는 이러한 고열부하시험을 수행함에 있어 고려해야 할 여러 가지 요소에 대해 논의하였다. 우선 인가하는 열유속(heat flux) 값은 일차적으로 시험시설의 최대 출력에 의해 좌우되며, 시험대상물의 운전조건 및 열부하 반복횟수에 의해 결정된다. 열부하 반복횟수는 주어진 열유속 값에 대해 total strain이 파단에 이르는 수준에 의해 결정된다. 열부하를 인가하는 시간은 히터에 전류를 인가했을 때 요구되는 온도로 상승하는 데 걸리는 시간과 시험대상물의 온도가 더 이상 증가하지 않는데 걸리는 시간에 의해 좌우된다. 냉각시간은 길수록 시험대상물의 온도가 냉각수의 온도에 접근하게 되나 너무 길어지면 시험시간이 급격히 증가하게 되므로, 온도 감소 곡선을 검토하여 적절한 시간을 정하게 된다. 열유속 측정은 냉각수의 온도 상승값과 유량으로부터 계산하게 되며, 정확한 측정을 위해서는 열부하를 인가하는 시간이 충분히 길어야 한다. 또한 시험대상 부품에서 열부하가 인가되는 면적을 정확히 정의해야 하며, 냉각관로에 열부하가 인가되어서는 않된다. 또한 시험대상부품을 지지하는 지지구조체를 통한 열손실을 최소화해야 정확한 열유속을 측정할 수 있다. 시험대상부품을 설치할 때 히터와의 간격 또한 결정해야 할 중요한 요소이며, 간격이 좁을수록 최대 열유속 값을 증가시킬 수 있으나, 너무 가까운 경우 히터의 열변형에 의한 접촉 및 아크 방전의 가능성이 있으며, 이 경우 히터와 시험대상부품의 손상을 가져오게 된다. 시험대상물이 국제열핵융합로(ITER)의 일차벽과 같이 베릴륨이 포함되어 있는 경우 방전에 의한 손상은 인체에 유해한 오염의 원인이 될 수 있다. 또한 순간적인 방전은 고가의 고전류전원의 고장을 유발할 수도 있다. 열부하 시험 중 시험대상물의 온도를 정확히 측정하는 것은 필수적이며, 온도 변화 곡선으로부터 시험대상물의 건전성 여부를 판단할 수 있다. 이를 위해 변화를 가장 잘 탐지 할 수 있는 위치에 온도 센서를 설치하는 것이 관건이며, 이는 사전 분석을 통해 알 수 있다.

• Journal of Welding and Joining
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• v.35 no.1
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• pp.55-60
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• 2017

There are many Industry Code and Standard (ICS) for Structural Integrity Assessment (SIA) on welded structure with defect. The general ICSs, such as R6, BS 7910 and API 579-1/ASME FFS-1, provide equations to determine the upper bound residual stress profiles based on collections from many literatures. However, these residual stress profiles used in the SIA cause the conservative design for welded structures. In this study, the structural integrity assessment for girth weld in pipeline has been conducted based on fracture mechanics. In addition, thermo-elastic plastic FE analysis was performed for evaluating the residual stress of girth weld in pipeline. The weight function solution is used to determine the stress intensity factor using the residual stress profile obtained by the FE analysis. This approach can account for redistribution and relaxation of residual stress as the defects grow. In order to the evaluate quantitative comparison between BS 7910 and weight function solution, structural integrity assessment determining allowable crack size on cracked pipe was performed with failure assessment diagram.

• Journal of Ocean Engineering and Technology
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• v.23 no.1
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• pp.122-128
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• 2009

In this study, damage detection method using harmony search method and frequency response is proposed. In order to verify this method, the following approaches are implemented. Firstly, damage detection method using harmony search was developed. To detect damage, objective functions that minimize difference with natural frequency and modal strain energy from undamaged and damaged model are used. Secondly, efficiency of developed damage detection method was verified by damage detection of beam structure. And results of harmony search and micro genetic algorithm are compared and evaluated. Thirdly, numerical model was implemented for harbor caisson structure and damage scenario was determined. Lastly, damage detection was performed by proposed method and utility of proposed method is verified.