• 비파괴검사학회지
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• 제19권6호
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• pp.411-419
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• 1999

에너지 변환설비와 관련된 기계구조물의 내열재료는 $350^{\circ}C{\sim}550^{\circ}C$의 온도범위에서 장시간 사용되는데 이때 조직의 결정입계에는 불순물 원소(P, Sn, Sb등)의 편석과 탄화물의 석출 등으로 인하여 재료의 취화 현상이 발생되고, 그로 인해 입계강도의 저하가 초래된다. 따라서 노후화된 고온설비의 안전성 및 효율적인 운전조건을 확보하고, 취성파괴 방지를 위해서는 취화손상의 정량적 평가는 매우 중요하다. 그러나 가동중인 고온설비에서 파괴시험을 위한 대량의 시험편채취가 거의 불가능한 경우가 대부분이므로 비파괴적인 시험방법이 요구된다. 본 연구에서는 인공시효열처리된 2.25Cr-1Mo강의 비파괴적인 취화손상도 평가를 위해 적정 부식환경하에서 전기화학적 분극시험 방법에 의한 최적의 평가인자를 조사하였다. 또한 전기화학 시험결과들은 준비파괴시험인 SP시험에 의한 취화도 평가결과와 비교되었다.

• 한국압력기기공학회 논문집
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• 제14권1호
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• pp.1-7
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• 2018

Materials in nuclear power plants can be embrittled by neutron irradiation. According to existing studies, the effect of the material property by irradiation embrittlement can be approximately simulated by cold working (pre-strain). In this study, finite element damage analysis method using the stress-modified fracture strain model is proposed to predict J-Resistance curves of irradiated SUS316 stainless steel. Experimental data of pre-strained SUS316 stainless steel material are obtained from literature and the damage model is determined by simulating the tensile and fracture toughness tests. In order to consider damage caused by the pre-strain, a pre-strain constant is newly introduced. Experimental J-Resistance curves for various degrees of pre-strain are well predicted.

• 한국기계가공학회지
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• 제15권3호
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• pp.72-78
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• 2016

In this study, we analyzed the accidental hydrogen embrittlement affecting the track nut on a self-propelled howitzer. Tracks are key components to maintain a high degree of confidence in the operation of the self-propelled howitzer and the safety of the crew. This study analyzed the fractured surface using SEM to review accidental damage of the wedge nut. In addition, we conducted revival tests and analyzed the results to identify the cause of the wedge nut damage from hydrogen embrittlement. We should carry out factor analysis and continuous improvement of the manufacturing process to determine the accidental breakage mechanism for future enhancement of the self-propelled howitzer. This study will be the useful reference for enhancing process designs in similar products.

• 한국압력기기공학회 논문집
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• 제19권2호
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• pp.117-129
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• 2023

Hydrogen embrittlement of a pipe is an important factor in hydrogen transport. To characterize hydrogen embrittlement, tensile and fracture toughness tests should be conducted. However, in the case of hydrogen-embrittled materials, it is difficult to perform tests in hydrogen environment, particularly at low temperatures. It would be useful to develop a methodology to predict the fracture toughness of hydrogen-embrittled materials at low temperatures using more efficient tests. In this study, the fracture toughness of API X52 steels in hydrogen at low temperatures is predicted from numerical simulation using coupled finite element (FE) damage analyses with FE diffusion analysis, calibrated by analyzing small punch test data.

• Nuclear Engineering and Technology
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• 제41권1호
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• pp.11-20
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• 2009

Radiation effects on materials are inherently multiscale phenomena in view of the fact that various processes spanning a broad range of time and length scales are involved. A multiscale modeling approach to embrittlement of pressure vessel steels is presented here. The approach includes an investigation of the mechanisms of defect accumulation, microstructure evolution and the corresponding effects on mechanical properties. An understanding of these phenomena is required to predict the behavior of structural materials under irradiation. We used molecular dynamics (MD) simulations at an atomic scale to study the evolution of high-energy displacement cascade reactions. The MD simulations yield quantitative information on primary damage. Using a database of displacement cascades generated by the MD simulations, we can estimate the accumulation of defects over diffusional length and time scales by applying kinetic Monte Carlo simulations. The evolution of the local microstructure under irradiation is responsible for changes in the physical and mechanical properties of materials. Mechanical property changes in irradiated materials are modeled by dislocation dynamics simulations, which simulate a collective motion of dislocations that interact with the defects. In this paper, we present a multi scale modeling methodology that describes reactor pressure vessel embrittlement in a light water reactor environment.

• 동력기계공학회지
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• 제19권5호
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• pp.60-66
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• 2015

Embrittlement of material by hydrogen charging should be cleared for safety of storage vessel of hydrogen and components deal with hydrogen. A stainless steel is generally used as materials for hydrogen transportation and storage, and it has a big advantage of corrosion resistance due to nickel component in material. In this study, microscopic damage behavior of stainless steel according to the hydrogen charging time using nondestructive evaluation was studied. The surface of stainless steel became more brittle as the hydrogen charging time increased. The parameters of nondestructive evaluation were also changed with the embrittlement of stainless steel surface by hydrogen charging. Ultrasonic test, which is the most generalized nondestructive technique, was applied to evaluate the relationship between the ultrasonic wave and mechanical properties of stainless steel by hydrogen charging. The attenuation coefficient of ultrasonic wave was increased with hydrogen charging time because of surface embrittlement of stainless steel. In addition, acoustic emission test was also used to study the dynamic behavior of stainless steel experienced hydrogen charging. AE event at the hydrogen charged specimen was obviously decreased at the plastic zone of stress-strain curves, while the number of event for the specimen of hydrogen free was dramatically generated when compared with the specimens underwent hydrogen charging.

• Nuclear Engineering and Technology
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• 제45권3호
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• pp.311-322
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• 2013

High-Cr martensitic steel HT-9 is one of the candidate materials for advanced nuclear energy systems. Thanks to its excellent thermal conductivity and irradiation resistance, ferritic/martensitic steels such as HT-9 are considered for in-core applications of advanced nuclear reactors. The harsh neutron irradiation environments at the reactor core region pose a unique challenge for structural and cladding materials. Microstructural and microchemical changes resulting from displacement damage are anticipated for structural materials after prolonged neutron exposure. Consequently, various irradiation effects on the service performance of in-core materials need to be understood. In this work, the fundamentals of radiation damage and irradiation effects of the HT-9 martensitic steel are reviewed. The objective of this paper is to provide a background introduction of displacement damage, microstructural evolution, and subsequent effects on mechanical properties of the HT-9 martensitic steel under neutron irradiations. Mechanical test results of the irradiated HT-9 steel obtained from previous fast reactor and fusion programs are summarized along with the information of irradiated microstructure. This review can serve as a starting point for additional investigations on the in-core applications of ferritic/martensitic steels in advanced nuclear reactors.

• 에너지공학
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• 제18권1호
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• pp.49-55
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• 2009

금속의 수소취화는 수소를 사용하는 설비의 안전성을 위협하는 중요한 문제이므로, 수소 환경에서 금속의 취화평가법에 관한 연구의 필요성이 요구되고 있다. 수소사회를 대비하기 위하여 대용량의 수소공급방법에 관한 연구가 진행되고 있는데, 기존의 천연가스 배관을 통한 공급방안이 검토되고 있다. 본 연구에서는 배관 내부에 수소혼합가스가 흐르면 배관모재부 및 용접부의 손상이 우려되므로, 국내에 건설되어 운용되고 있는 X65 천연가스 배관의 모재부를 대상으로 수소취화 거동에 대하여 연구하였다. 재료의 수소침투는 전기분극법을 사용하였으며 강도평가에는 소형펀치시험법을 사용하였다. 수소장입량의 증가에 따라서 금속의 강도가 저하되는 현상이 발견되는 재료도 있으나, 본 연구에 사용한 X65강의 모재부에서 수소취화의 영향은 거의 나타나지 않았으므로 수소영향에 의한 X65강 모재부의 강도저하는 발생하지 않는 것으로 판단된다. 또한 소형펀치시험을 이용함으로써 금속재료의 수소취화에 의한 기계적 강도변화를 평가할 수 있었다.

• 대한기계학회논문집A
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• 제37권6호
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• pp.753-760
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• 2013

금속 재료의 수소취화 현상에 대한 분석은 수소플랜트의 안전성 평가를 위해 매우 중요하다. 수소환경하 취화된 재료의 기계적 물성과 파괴인성은 구조 건전성 평가에 가장 기본적이며 중요한 자료이다. 본 논문은 최근에 개발된 유한요소 해석 기반 현상학적 손상해석을 소형펀치 실험에 적용하고 Inconel 617 재료의 대기 중 소형펀치 실험결과와 비교 함으로써 손상해석 기법의 적용 타당성을 보였다. 또한 역변환 기법을 사용하여 소형펀치 실험으로부터 인장물성을 예측하고 인장실험으로부터 구한 재료 물성과 비교하여 적용 가능성을 검증하였다. 검증된 결과를 바탕으로 수소취화된 시편에 대한 소형펀치 실험결과에 역변환 기법과 손상해석을 적용하여 수소취화 된 재료의 기계적물성과 파괴인성을 예측하였다.

• Journal of Advanced Marine Engineering and Technology
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• 제38권8호
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• pp.974-980
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• 2014

Aluminum acts as sacrificial anode and corrosion protection with Al2O3 formation. If the same current on material for Al ships with steel ships supplies, the more hydrogen would be occurred, that result is bring about over-protection. For this reason, the damage by hydrogen embrittlement leads to the serious accident. In this study, we evaluate electrochemical behavior with rotation speed of 5083-H116 Al alloy material for Al ship in seawater. To examine the electrochemical characteristics with rotation speed and its effects on performance, experiments were conducted at four rotation speed. Results of experiments, the corrosion current density and damage were increased by applying the rotation speed compared to static state.