• 제목/요약/키워드: 용접부 검사

검색결과 195건 처리시간 0.024초

모의 시험편에 대한 TOFD와 방사선투과시험의 비교 (Comparison of TOFD and Radiographic Testing for a Mock-up Specimen)

  • 김중직;전종건;김진택
    • 비파괴검사학회지
    • /
    • 제28권1호
    • /
    • pp.64-69
    • /
    • 2008
  • 압력용기 및 구조물 용접부의 내부결함을 검출하기 위해서는 방사선투과시험과 초음파탐상시험을 시행한다. 그러나 방사선투과시험은 방사선 노출 위험성과 필름 현상처리 소요 등으로 결과의 확인에 상대적으로 긴 시간이 소요되어 제작 공정에 영향을 준다. 일반적인 수동 초음파탐상시험은 결과의 재현이 용이하지 않으며 검사자의 기량에 대한 의존도가 높다는 문제점을 가지고 있다. 이에 대한 대안으로 자동 초음파탐상시험 기법의 하나인 TOFD의 적용이 확산되고 있다. 본 연구는 결함을 포함한 시험편에 대하여 방사선투과 시험과 TOFD 기법을 적용하고 비교한 결과를 기술하였다. TOFD 기법은 초음파 시험기법의 객관적 신뢰도 향상에 기여하게 될 것으로 판단된다.

T형상용접 이음에서 매몰된 라멜라균열이 용접부의 기계적 강도에 미치는 영향 (Effects of the buried lamellar tears on the mechanical strength in the welded T joints)

  • 고진현
    • Journal of Welding and Joining
    • /
    • 제6권4호
    • /
    • pp.44-53
    • /
    • 1988
  • The mechanical strengths of buried lamellar tears located near the weld toe in the welded tee joints were evaluated in terms of the loss of load carrying capacity as a function of tear area. In static loading, the load carrying capacity was significantly reduced when tear intercepted over 10% of the cross-sectional area of the welded joints. However, the welded joints containing buried tears still failed at stresses over the yield strength of the base metal in the through-thickness direction in spite of the presence of tears up to 20-25% of the area. Fatigue strength of welded joints containing tears markedly reduced with increasing tear areas. Lehigh lamellar tearing test used in this study to produce speicmens was described in detail. The load carrying cpapacity in static loading was influenced by the reduction of supporting area whereas that in fatigue loading was influenced by the stress-concentration effects of lamellar tears and the reduction of supporting area. In bend tests, the pre-existing lamellar tears always grew up toward the weld toe. However, in fatigue loading, cracks grew up and down simultaneously form both the weld toe and the top of lamellar tears because of stress concentration. In fatigue loading, delaminations and decohesion of inclusion/matrix interface generated in multipass welds provided crack propagation paths and enhanced crack propagation because the tips of delaminations and deconhesios acted as stress raisers.

  • PDF

저주파수 TRL 탐촉자를 이용한 Cast Stainless Steel 배관 용접부 초음파탐상기법 (UT Inspection Technique of Cast Stainless Steel Piping Welds Using Low Frequency TRL UT Probe)

  • 신건철;장희준;전영철;노익준;이동진
    • 한국압력기기공학회 논문집
    • /
    • 제6권1호
    • /
    • pp.29-36
    • /
    • 2010
  • Ultrasonic inspection of heavy walled cast austenitic stainless steel(CASS)welds is very difficult due to complex and coarse grained structure of CASS material. The large size of anisotropic grain strongly affects the propagation of ultrasound by severe attenuation, change in velocity, and scattering of ultrasonic energy. therefore, the signal patterns originated from flaws can be difficult to distinguish from scattered signals. To improve detection and sizing capability of ID connected defect for heavy walled CASS piping welds, the low frequency segmented TRL Pulse Echo and Phased Array probe has been developed. The experimental studies have been performed using CASS pipe mock-up block containing artificial reflectors(ID connected EDM notch). The automatic pulse echo and phase array technique is applied the detection and the length sizing of the ID connected artificial reflectors and the results for detection and sizing has been compared respectively. The goal of this study is to assess a newly developed ultrasonic probe to improve the detection ability and the sizing of the crack in coarse-grained CASS components.

  • PDF

용접부 비파괴 검사의 신뢰성 비교: 화력 발전소의 보일러 수냉벽 배관 사례연구 (Comparative Reliability of Nondestructive Testing for Weld: Water Wall Tube in Thermal Power Plant Boiler Case Study)

  • 최창덕;임익성
    • 한국신뢰성학회지:신뢰성응용연구
    • /
    • 제18권3호
    • /
    • pp.240-249
    • /
    • 2018
  • Purpose: The purpose of this research is to find which technique, between the PAUT (Phased array ultrasonic test) that has been used widely in practice and RT (Radiographic test) that was used widely in the past, has the higher reliability as a non-destructive testing of welding points in water wall tubes. Methods: To evaluated the reliability of non-destructive testing, eleven test pieces that were fabricated intentionally, which have the most frequently occurred defect types in water wall tubes and then both the PAUT and RT were performed on those eleven test pieces to compare their reliability. Results: The differences of type of defect, length are occurred due to the characteristics of nondestructive testing. The RT could not detect the lack of fusion defect type in specimen #4 and #8 while PAUT could not detect the lateral crack and 1 mm size small porosity in specimen #11. Conclusion: It is concluded that applying both the RT and PAUT result the best reliability rather than applying only one test method, if it is possible, in nondestructive testing of weld water wall tube in thermal power plant boiler case.

초음파 DAC 기법을 이용한 압력용기 용접부의 지시 크기측정 정확도 평가 (Accuracy of Ultrasonic Flaw Sizing using DAC Techniques for Pressure Vessels Welds of Nuclear Power Plant)

  • 김재동;임형택;도의순
    • 한국압력기기공학회 논문집
    • /
    • 제11권2호
    • /
    • pp.20-24
    • /
    • 2015
  • During refueling Outage, In-service inspections(ISIs) for the Nuclear Power Plant components are mandatory requirement in accordance with ASME Code Sec. XI. Especially, in current ultrasonic testing is one of the most important NDT techniques that are used for volumetric examination methods for nuclear power plant components, and accurate sizing of flaw indication by UT is essential to assure the integrity of the components. However, ASME code specifies minimum requirement for vessel examination procedure, and so far many different flaw sizing approaches have been tried to apply. Through the Round Robin Test(RRT), the accuracy of ultrasonic flaw sizing using DAC techniques was measured with the mock-ups simulating typical pressure vessel welds. These mock-ups contain artificially introduced flaws of known size and location. This paper shows experimental comparison data on the accuracy of techniques using such as 6dB drop, 50%DAC, 20%DAC and 20%DAC with beam spread correction, and also shows that diverse DAC techniques can be effectively applied to the assessment of the flaw sizing for pressure vessel welds in the stage of welding and fabrication.

닫힘균열의 1차원 모델을 이용한 고조파 발생에 대한 파라미터 연구 (Parameter Study of Harmonics Generation Using One-dimensional Model of Closed Crack)

  • 양승용;김노유
    • 한국철도학회논문집
    • /
    • 제14권5호
    • /
    • pp.398-403
    • /
    • 2011
  • 균열이 용접부 내와 같은 잔류응력의 영향을 받는 곳에 존재할 경우, 균열은 닫힘균열로 존재할 수 있으며, 인장과 압축에 대하여 비대칭적인 거동을 보이게 된다. 이러한 비선형 균열에 대하여 균열면에서 발생하는 고조파를 이용한 초음파 탐지 기법이 활발히 연구되고 있다. 본 연구에서는 비선형 접촉면에서 발생하는 고조파에 대한 파라미터 연구를 수행하였다. 본 연구는 일반적인 3차원 균열로 나아가기 위한 기초연구의 성격을 띄고 있다. 압축과 인장에 대해 각기 다른 선형 거동을 나타내는 접촉면을 가정하였고 1차원 문제를 고려하였다. 기본주파수 성분에 대한 2차고조파 성분의 비를 다양한 강성비, 입사파의 주파수, 접촉면의 두께에 대하여 조사 하였다.

한국표준형 원전 증기발생기 Stay 용접부 자동검사시스템 및 현장 검증 (Field Application of Ultrasonic Inspection System for Stay Welds at Steam Generator of KSNP)

  • 임사회;박치승;박철훈;주금종;노희충;윤광식
    • 한국압력기기공학회 논문집
    • /
    • 제6권1호
    • /
    • pp.37-42
    • /
    • 2010
  • The stay cylinder weld at the steam generator of Korean Standard Nuclear Power Plants is safety class I component and is subjected to be inspected by the volumetric examination such as ultrasonic method. As accessibility of this area is limited due to the narrow space and high radiation, the existing manual inspection method involves various difficulties. Moreover operators may be exposed to internal contamination by contaminated dust during the surface buffing process to improve the inspection reliability of this area. Recently the new automatic inspection system for stay cylinder welds has been developed. The inspection system basically consists of a driving assembly, data acquisition device and signal processing units. The driving assembly is classified by 1) the scanner for inspecting and buffing the weld, 2) pillars for guiding the scanner and 3) the base frame for loading and supporting pillars. The scanner has 4 sensor modules to inspect in 4 refracted angles and 4 incident directions. These components can be inserted into the skirt of the stay cylinder through the manway hole and assembled easily by one-touch in the skirt. Data acquisition device and signal processing units developed in previous works are also newly upgraded for better processing of data analysis and evaluation. The system has been successfully demonstrated not only in the mock-up but also in the field. In this paper, newly developed inspection system for the stay cylinder weld of the steam generator is introduced and their field applications are discussed.

  • PDF

원전 가압기 노즐 및 안전단 재료에 대한 기계적 물성시험 연구 (A Study for Experiment to Measure Mechanical Properties of Pressurizer Nozzle and Safety-Ends in Nuclear Power Plant)

  • 이경수;이성호;김진원
    • 비파괴검사학회지
    • /
    • 제33권2호
    • /
    • pp.147-153
    • /
    • 2013
  • 최근 가압경수로형 원전의 가압기 노즐과 안전단 사이의 이종용접부에서 일차수응력부식균열에 대한 건전성 확보가 중요한 관심사항으로 대두되고 있다. 가압기 노즐은 SA508 Gr.3 저합금강이며 안전단은 F316L 스테인리스강으로, 이들 두 재료 사이에 용접재로는 Alloy 82/182가 사용되었다. 재료 결함에 대한 건전성 평가를 위해서는 재료의 기계적 물성치, 특히 인장물성과 파괴물성이 확보되어야 한다. 그러나, 일반적인 재료 규격과 시험성적서에서는 상온의 인장물성이 제공되지만 고온의 인장물성과 파괴인성이 제공되지 않는다. 따라서, 본 논문에서는 상온과 원전 운전온도에서 SA508 Gr.3과 F316L 스테인리스강에 대한 인장시험과 J-R 파괴인성시험을 수행하고 그 결과를 수록하였다.

원자로냉각재계통 3" 분기관 용접부 위상배열초음파탐상검사(PAUT)기법 개발 (Development of the Phased Array Ultrasonic Test Technique for the Weld Inspection of Reactor Coolant System 3" Branch Connection Lines in Nuclear Power Plants)

  • 이승표;문용식;정남두;조용배;김창수
    • 한국압력기기공학회 논문집
    • /
    • 제4권2호
    • /
    • pp.40-45
    • /
    • 2008
  • There exist many types of pipe and component fatigue through vibrations, thermal fatigues or shifting. In some cases of thermal stratification/thermal fatigue, pipes & components are receiving thermal stress by means of material expansion and shrinkage by continuous thermal repetitive variation. Small cracks initially occur on the inside surface by thermal stress. These cracks grow in depth the pipe wall and finally come to a rupture. Pipe parts of susceptibility to thermal stratification and thermal fatigue are now being examined by conventional UT(ultrasonic test) as volumetric examination. It is difficult to fully satisfy the code & standards requirements because 3" weldolet weldments of RCS 16" pipe to 3" branch connection lines have complex structural shape. To solve the problems of conventional UT examination, we made a realistic mock-up and UT calibration block. We performed a simulation of phased array UT utilizing CIVA as NDE(Non-Destructive Examination) simulation software. Also we designed phased array UT transducer and wedge, optimal frequency by using simulation data. We performed phased array UT experiment through mock-up including artificial flaws(notch). The phased array UT technique is finally developed to improve the reliability of ultrasonic test at RCS 16" pipe to 3" branch connection weld.

  • PDF

가압기 전열기 슬리브 및 J-Groove 용접부의 자동 초음파검사 (Automatic Ultrasonic Inspection on Heater Sleeves and J-Groove Welds of Pressurizer)

  • 류승우;장희준;김선제;이상덕;성종환
    • 한국압력기기공학회 논문집
    • /
    • 제6권2호
    • /
    • pp.20-27
    • /
    • 2010
  • In order to prevent the corrosion of component contacted primary water designed alloy 600 material in the nuclear power plant. But the primary water stress corrosion cracking(PWSCC) of alloy 600 and weld area occurs continuously due to the residual stress. The leakage accident resulted from PWSCC in the drain nozzle of the steam generator of domestic power plants. Heater sleeves of the pressurizer are welded with alloy 600 weld material and therefore exposed to the primary water environment. PWSCC occurred in heater sleeve material and weld area of many foreign power plants. The current issue of domestic nuclear power plants are consequently concentrated to PWSCC of similar material. In order to improve the detection and the sizing of the PWSCC in the welding sleeve of the pressurizer, the automatic UT system and multi-directions probe sets have been developed. The experimental studies have been performed using the mock-up block containing artificial reflectors(ID connected EDM notch) and semi-artificial cracks made from thermal fatigue. The automatic UT System is applied in the detection and the length sizing of the ID/OD on the tube and the J-groove weld area of the artificial reflectors and results of the detection and the sizing are compared respectively. Also, the developed automatic UT system is successfully accomplished to inspect the heater sleeve and the J-groove weld area on the pressurizer for the detection of PWSCC.

  • PDF