• 제목/요약/키워드: Thermal Fatigue

검색결과 573건 처리시간 0.027초

인공해양환경에서 플라즈마 아크 용사 공법이 적용된 Al 및 Zn 코팅의 부식 방지 성능 평가 (Anti Corrosive Performance of Al and Zn Coatings Deposited by Plasma Arc Thermal Spray Process in Artificial Ocean Water)

  • 잔낫;이한승
    • 한국건축시공학회:학술대회논문집
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    • 한국건축시공학회 2020년도 가을 학술논문 발표대회
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    • pp.52-53
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    • 2020
  • The thermal spray coating process is being used to protect the metals and alloys from wear, abrasion, fatigue, tribology, and corrosion failure. Therefore, in the present study, Al and Zn was deposited by plasma arc thermal spray process onto the steel substrate and their performance was assessed. The bond adhesion result shows that Al coating has higher value attributed to compact, dense, and less porous compared to Zn coating which contain defects/pores and uneven morphology assessed by scanning electron microscopy (SEM). Electrochemical results show that the Al coating exhibited higher impedance value compared to Zn in artificial ocean water solution at prolonged exposure periods. However, both coatings show the increment in polarization resistance with exposure periods which reveal that porosity of coatings is filled by the corrosion products.

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원전 안전주입배관에서의 열성층 유동해석 (Analysis for the Behavior of Thermal Stratification in Safety Injection Piping of Nuclear Power Plant)

  • 박만흥;김광추;염학기;김태룡;이선기;김경훈
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2001년도 춘계학술대회논문집D
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    • pp.110-114
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    • 2001
  • A numerical analysis has been perfonned to estimate the effect of turbulent penetration and thermal stratified flow in the branch lines piping. This phenomenon of thermal stratification are usually observed in the piping lines of the safety related systems and may be identified as the source of fatigue in the piping system due to the thermal stress loading which are associated with plant operating modes. The turbulent penetration length reaches to $1^{st}$ valve in safety injection piping from reactor coolant system (RCS) at normal operation for nuclear power plant when a coolant does not leak out through valve. At the time, therefore, the thermal stratification does not appear in the piping between RCS piping and $1^{st}$ valve of safety injection piping. When a coolant leak out through the $1^{st}$ valve by any damage, however, the thermal stratification can occur in the safety injection piping. At that time, the maximum temperature difference of fluid between top and bottom in the piping is estimated about $50^{\circ}C$.

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Numerical analysis of temperature fluctuation characteristics associated with thermal striping phenomena in the PGSFR

  • Jung, Yohan;Choi, Sun Rock;Hong, Jonggan
    • Nuclear Engineering and Technology
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    • 제54권10호
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    • pp.3928-3942
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    • 2022
  • Thermal striping is a complex thermal-hydraulic phenomenon caused by fluid temperature fluctuations that can also cause high-cycle thermal fatigue to the structural wall of sodium-cooled fast reactors (SFRs). Numerical simulations using large-eddy simulation (LES) were performed to predict and evaluate the characteristics of the temperature fluctuations related to thermal striping in the upper internal structure (UIS) of the prototype generation-IV sodium-cooled fast reactor (PGSFR). Specific monitoring points were established for the fluid region near the control rod driving mechanism (CRDM) guide tubes, CRDM guide tube walls, and UIS support plates, and the normalized mean and fluctuating temperatures were investigated at these points. It was found that the location of the maximum amplitude of the temperature fluctuations in the UIS was the lowest end of the inner wall of the CRDM guide tube, and the maximum value of the normalized fluctuating temperatures was 17.2%. The frequency of the maximum temperature fluctuation on the CRDM guide tube walls, which is an important factor in thermal striping, was also analyzed using the fast Fourier transform analysis. These results can be used for the structural integrity evaluation of the UIS in SFR.

Mod.9Cr-1Mo 강 구조의 크리프-피로 균열 거동 평가법 개발 (Development of Assessment Methodology on Creep-Fatigue Crack Behavior for a Grade 91 Steel Structure)

  • 이형연;이재한
    • 대한기계학회논문집A
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    • 제34권1호
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    • pp.103-110
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    • 2010
  • 본 연구에서는 프랑스의 RCC-MR A16 절차에 기초하여 Mod.9Cr-1Mo 강(ASME Grade 91) 구조의 크리프-피로 균열 개시 및 성장 평가법을 확장 개발하였다. 현재의 A16 지침은 오스테나이트 스테인리스강에 대해서만 크리프-피로 균열 개시 및 성장 평가법을 제시하고 있지만, 현재 초초임계(USC) 화력발전소는 물론 미래형 원자로 시스템의 구조재료로서 폭넓게 채택되고 있는 Mod.9Cr-1Mo 강에 대한 지침은 제시하지 않고 있다. 본 연구에서는 FMS(페리틱-마르텐사이트강)에 대한 크리프-피로 균열 개시 및 성장 평가법을 제시하고 있고, 구조물에 대한 크리프-피로 균열 거동 평가를 수행하였다. 평가결과는 구조시험을 수행한 결과 얻은 관찰 이미지와 비교하였다.

기계적 피로결함 시험편 제조 및 결함 크기 평가 (Fabrication of Mechanical fatigue flawed Specimen and Evaluation of Flaw Size)

  • 홍재근;김우성;손영호;박반욱
    • 비파괴검사학회지
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    • 제23권1호
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    • pp.38-44
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    • 2003
  • 원자력발전소의 안전성등급 기기에 적용되는 비파괴검사는 실제 결함을 실현한 시험편을 사용하여 결함탐지능력을 검증하도록 하는 기량검증이 요구되고 있다. 가동중인 원전에서 발생 가능한 균열으로는 기계적 피로균열, 열 피로균열 및 입계부식균열 등이 있으나 본 연구에서는 기계적 피로균열을 대상으로 하였다. 인장 피로하중을 사용하여 기계적 피로결함을 제조하기 위해서 시험편을 설계하였고 원하는 피로결함 파면의 조도를 얻기 위해서 인가하중의 크기 및 사이클 수를 조절하여 피로결함을 발생시켰다. 발생된 결함에 대한 정확한 크기와 위치에 대한 물리적 정보를 얻은 후에 결함이 설계된 크기와 위치에 존재하도록 기밀용접을 실시하였다. 기밀용접 후 잔여 용접 흠은 가스 텅스텐 아크용접 및 플럭스 코어드 아크용접으로 채워졌다. 최종 완성된 피로결함 시험편을 방사선투과검사 및 초음파탐상검사를 통하여 검사한 결과, 설계된 길이와 깊이로 피로결함이 형성되었음을 확인하였다.

운전이력을 고려한 지역난방 열배관의 피로수명 평가 및 관리 체계 구축 (Establishment of Fatigue Life Evaluation and Management System for District Beating Pipes Considering Operating Temperature Transition Data)

  • 장윤석;정성욱;김형근;최재붕;김상호;김연홍;김영진
    • 대한기계학회논문집A
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    • 제29권9호
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    • pp.1235-1242
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    • 2005
  • A district heating(DH) system supplies environmentally-friend heat and is appropriate for reduction of energy consumption and/or air pollutions. The DH transmission pipe, composed of supply and return pipes, has been used to transmit the heat and prevent heat loss during transportation. The two types of pipes are operated at a temperature of $75\~115^{\circ}C\;and\;40\~65^{\circ}C$, respectively, with an operating pressure of less than 1.568MPa. The objectives of this paper are to systematize data processing of transition temperature and investigate its effects on fatigue life of DH pipes. For the sake of this, about 5 millions temperature data were measured during one year at ten locations, and then available fatigue lift estimation schemes were examined and applied to quantify the specific thermal fatigue life of each pipe. As a result, a relational database management system as well as reliable fatigue lift evaluation procedures is established for Korean DH pipes. Also, since the prototypal evaluation results satisfied both cycle-based and stress-based fatigue criteria, those can be used as useful information in the future fer optimal design, operation and energy saving via setting of efficient condition and stabilization of water temperature.

장경간 강바닥판 케이블교량에 적용하기 위한 폴리우레탄 폴리머콘크리트의 공용특성 연구 (A Study to Evaluate Performance of Poly-Urethane Polymer Concrete for Long-Span Orthotropic Steel Bridge)

  • 박희영;이정훈;곽병석;최이현;김태우
    • 한국도로학회논문집
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    • 제15권1호
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    • pp.1-9
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    • 2013
  • PURPOSES: The purpose of this study is to evaluate physical properties, durability, fatigue resistance, and long-term performance of poly-urethane concrete (PU) which can be possible application of thin layer on long-span orthotropic steel bridge and to check structural stability of bridge structure. METHODS : Various tests of physical properties, such as flexural strength, tensile strength, bond strength and coefficient of thermal expansion tests were conducted for physical property evaluation using two types of poly urethane concrete which have different curing time. Freezing and thawing test, accelerated weathering test and chloride ion penetration test were performed to evaluate the effect of exposed to marine environment. Beam fatigue test and small scale accelerated pavement test were performed to assess the resistance of PU against fatigue damage and long-term performance. Structural analysis were conducted to figure out structural stability of bridge structure and thin bridge deck pavement system. RESULTS: The property tests results showed that similar results were observed overall however the flexural strength of PUa was higher than those of PUb. It was also found that PU materials showed durability at marine environment. Beam fatigue test results showed that the resistances of the PUa against fatigue damage were two times higher than those of the PUb. It was found form small scale accelerated pavement test to evaluate long-term performance that there is no distress observed after 800,000 load applications. Structural analysis to figure out structural stability of bridge structure and thin bridge deck pavement system indicated that bridge structures were needed to increase thickness of steel deck plate or to improve longitudinal rib shape. CONCLUSIONS: It has been known that the use of PU can be positively considered to thin layer on long-span orthotropic steel bridge in terms of properties considered marine environment, resistance of fatigue damage and long-term performance.

원전 구조물 결함 탐지를 위한 음향방출 신호 처리 방안에 대한 기초 연구 (The Basic Study on the Method of Acoustic Emission Signal Processing for the Failure Detection in the NPP Structures)

  • 김종현;김재성;이정;곽노권;이보영
    • 비파괴검사학회지
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    • 제29권5호
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    • pp.485-492
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    • 2009
  • 열피로균열은 원자력발전소의 운영 과정에서 구조물의 수명을 결정짓는 문제로 정량적인 탐지가 어렵다. 현재 산업현장에서 구조물에 대한 건전성을 정량적으로 평가하기 위해서 radiographic탐상 및 초음파탐상, eddy current 등 다양한 종류의 비파괴검사 기술이 사용되고 있지만, 위에 열거한 비파괴탐상법의 경우 균열이 일정부분 진행된 이후에나 검출이 가능하다는 제한 사항이 있다. 이러한 이유로 구조물에 대한 연속적인 모니터링이 가능한 장점을 가진 음향방출탐상법(acoustic emission testing)이 대안적인 검사방법으로 제시되고 있다. 일반적으로 구조물이나 장비의 건전성에 영향을 미치는 모든 요인들이 음향방출 신호의 발생을 일으키기 때문에, 음향방출을 이용한 결함 탐상시 함께 발생하는 노이즈를 구분하는 일은 음향방출을 연구하는 대부분의 연구원의 주요 업무중 하나라고 할 수 있다. 이에 본 연구에서는 열피로 사이클 조건에서의 배관에 대한 음향방출 신호를 수집하여 유효한 균열 신호를 노이즈로부터 구분하고자 하는 목적으로 진행되었다. 그 방법으로 유사한 조건에서 실시한 결과를 이용하여 노이즈 필터링 조건을 설정하였으며, 균열의 신호를 찾아내기 위한 방법으로 음향파형(waveform) 구분법을 제시하였다. 이 실험에서 도출된 결과는 구조물의 결함을 탐지하는 실시간 연속적 모니터링 기술 개발에 대한 기초자료로 사용될 수 있을 것으로 기대된다.