• Title/Summary/Keyword: 연성-취성천이온도

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Evaluation of Microstructure and Ductile-Brittle Transition Temperature in Thermally aged 2.25Cr-1Mo Steel by Electrical Resistivity Measurement (전기비저항을 이용한 2.25Cr-1Mo 강 열화재의 미세조직 및 연성-취성천이온도 평가)

  • Byeon, Jai-Won;Kwun, S.I.
    • Journal of the Korean Society for Nondestructive Testing
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    • v.22 no.3
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    • pp.284-291
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    • 2002
  • An attempt was made to evaluate the degree of aging degradation in thermally aged 2.25Cr-1Mo steel by electrical resistivity measurement. Artificial aging was performed to simulate the microstructural degradation in 2.25Cr-1Mo steel arising from long time exposure at $540^{\circ}C$. Microstructural parameter (amount of solid solution element), mechanical property (ductile-brittle transition temperature) and electrical resistivity were measured to investigate the mutual relationship among these parameters. Depletion of solid solution element(Mo and Cr) in matrix was detected after aging. The ductile-brittle transition temperature(DBTT) increased rapidly in the initial stage of aging and then saturated afterward. On the other hand, the electrical resistivity decreased rapidly in the beginning and then saturated in the later stage of aging.

원자로 압력용기 감시시험용 충격시험시스템 구축

  • 주용선;박대규;안상복;홍권표;이기순
    • Proceedings of the Korean Nuclear Society Conference
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    • 1998.05b
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    • pp.118-123
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    • 1998
  • 원자로 압력용기 재료로 사용되고 있는 ASTM SA508 및 SA533 계열의 재료는 결정구조가 체심입방격자(bcc)로서 시험온도별 최대흡수에너지(USE)에 대한 선도를 그리면 고온에서는 연성이 크고, 저온에서는 취성이 큰 전형적인 “S”자 형태의 Cv-천이온도곡선으로 나타난다. 그리고 조사전과 조사후의 연성-취성천이온도곡선을 흡수에너지값이 30ft-lb 또는 50ft-lb인 지점에석 비교해보면 재료의 조사취화(radiation embrittlement)현상으로 온도가 높은 쪽으로 이동됨을 알 수 있으며, 이러한 온도의 이동값은 원자로의 운전수명과 밀접한 관련이 있다. 따라서 조사전후의 흡수에 너지값에 따른 온도변화량를 정확하게 산출하기 위해서는 시편의 온도를 조절하는 장치 및 시편을 아주 짧은 시간내에 충격시험기의 앤빌까지 장전하는 장치 둥의 충격시험시스템 구축은 매우 중요하다. 이에 조사계시험시설(IMEF)에서는 원자로 압력용기 감시시험에 대한 충격시험시스템을 구축하였고, 이의 내용은 감시시험 수행에 기준이 되는 ASTM El85-82 및 과학기술처 고시 제 92-20호의 세부내용을 충분하게 만족시키는 것으로 확인되었으며, 이렇게 확인된 내용들은 현재 국내에서 수행되고 있는 감시시험에 적극적으로 활용되고 있다.

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$RT_{NDT}$ 결정과 K 곡선 도출을 위한 통계적방법

  • 강성식;지세환;홍준화
    • Proceedings of the Korean Nuclear Society Conference
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    • 1995.05b
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    • pp.667-673
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    • 1995
  • 원자력 발전소의 안전성과 향후 수명연장에 있어 중요한 파괴인성 평가기준으로 사용되는 연성-취성 천이온도인 RT$_{NDT}$ 의 중요성과 값 결정에 있어서의 문제점을 살펴보고, 천이온도 영역에서 파괴인성의 통계적 분포를 이용한 RT$_{NDT}$ 예측과 충격시험결과로부터 K곡선을 유도하는 방법에 대한 가능성 등을 논의하였다.

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소형 펀치 시험에 의한 강용접부의 파괴강도 평가에 관한 연구 1

  • 유대영;정세희;임재규
    • Journal of Welding and Joining
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    • v.7 no.3
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    • pp.28-35
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    • 1989
  • It was reported that the toughness for welded region was influenced by various factors such as the gradient for prior austenite grain size, the variation of microhardness and the characteristic microstructure depending on distance from the fusion boundary. Therefore, in order to evaluate the fracture strength of the weldment in which the microstructures change continuously, it is important to assess the peculiar strength of each microstructure in welded region. It was known that the small punch(SP) test technique which was originally developed to study the irradiation damage effect for the structures of nuclear power plant was also useful to investigate the strength evaluating of nonhomogeneous materials. In this paper, by means of a small punch test technique the possibility of evaluating strength of parent and welded region in SS41 and SM53B steels was investigated. The obtained results are summerized as follows: 1) The small punch test which showed markedly the ductile-brittle transition behavior in this experiment may be applied to evaluation for the fracture strength of welded region. 2) It was shown that the ductile-brittle regime lied in Region III(plastic membrane stretching region) of the flow characteristics observed in SP test. 3) The SP test technique which shows a more precipitous energy change transition behavior than the other test technique is able to estimate the more precise transition temperature. 4) It could be seen that in comparision with the structure of parent the structure of weld HAZ in SS41 steel was improved while it in SM53B steel was deteriorated.

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Evaluation of the Ductile-Brittle Transition Behavior of fracture Toughness by Material Degradation (열화에 따른 파괴인성치의 연성-취성 천이거동 평가)

  • 석창성;김형익;김상필
    • Journal of the Korean Society for Precision Engineering
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    • v.20 no.5
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    • pp.140-147
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    • 2003
  • As the huge energy transfer systems like as nuclear power plant and steam power plant are operated for a long time at a high temperature, mechanical properties are changed and ductile-brittle transition temperature is raised by degradation. So it is required to estimate degradation in order to assess the safety, remaining life and further operation parameters. The sub-sized specimen test method using surveillance specimen was developed for evaluating the integrity of metallic components. In this study, we would like to present the evaluation technique of the ductile-brittle transition temperature by the sub-sized specimen test. The four classes of the thermally aged 1Cr-1Mo-0.25V specimens were prepared using an artificially accelerated aging method. The tensile test and fracture toughness test were performed. The results of the fracture toughness tests using the sub-sized specimens were compared with the evaluation technique of the ductile-brittle transition temperature.

The Evaluation of Ductile-Brittle Transition of Fracture Toughness by Material Degradation (재료열화에 따른 파괴인성치의 연성-취성 천이거동 평가)

  • Kim, Sang-Pil;Kim, Hyung-Ick;Seok, Chang-Sung
    • Proceedings of the KSME Conference
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    • 2001.06a
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    • pp.579-584
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    • 2001
  • As the huge energy transfer systems like as nuclear power plant and steam power plant are operated for a long time, mechanical properties are changed and ductile-brittle transition temperature is raised by degradation. So it is required to estimate degradation in order to assess the safety, remaining life, and further operation parameters. The sub-sized specimen test method using surveillance specimen was developed for evaluating the integrity of metallic components. In this study, we would like to present the evaluation technique of the ductile-brittle transition temperature by the sub-sired specimen test. The four classes of the thermally aged 1Cr-1Mo-0.25V specimens were prepared using an artificially accelerated aging method. The tensile test and fracture toughness test were performed. The results of the fracture toughness tests using the sub-sized specimens were compared with the evaluation technique of the ductile-brittle transition temperature.

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Study on Fracture Behavior of Mild Steel Under Cryogenic Condition (연강(Mild Steel)의 극저온 파괴 거동에 대한 실험적 연구)

  • Choi, Sung Woong;Lee, Woo IL
    • Journal of the Korean Institute of Gas
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    • v.19 no.6
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    • pp.62-66
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    • 2015
  • Considering for plants and structure under extreme conditions is required for the successful design, especially temperature and pressure. The ductile-brittle transition temperature (DBTT) for the materials under extreme condition needs to be considered. In this study, A-grade mild steel for the LNG carrier and offshore plant was examined by performing low-temperature Charpy V-notch (CVN) impact tests to investigate DBTT and the fracture toughness. The absorbed energy decreased gradually with the experimental temperature, which showed an upper-shelf energy region, lower shelf energy region, and transition temperature indicating DBTT. In addition, the fracture surface morphologies of the mild steels indicated ductile fractures at the upper-shelf energy level, with wide and large-sized dimples, whereas a brittle fracture surface, where was observed at the lower-shelf energy level, with both large and small cleavage facets. Based on the experimental results, ductile brittle transition temperature was estimated in about $-60^{\circ}C$.

Transition Temperature Evaluation of 1Cr-1Mo-0.25V Steel Using Miniaturized Charpy Impact Specimen (소형 샤르피 충격시험편을 이용한 1Cr-1Mo-0.25V강의 천이온도 평가)

  • Nahm Seung Hoon;Kim Si Cheon;Lee Hae Moo
    • Journal of the Korean Institute of Gas
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    • v.2 no.4
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    • pp.42-46
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    • 1998
  • Miniaturized specimen technology Permits mechanical behavior to be determined using a minimum volume of material. The technology is useful in case of not collecting a large amount of materials from industrial equipments. Five kinds of accelerated degradation materials were prepared by isothermal aging heat treatment at $630^{\circ}C$. Three kinds of specimens were prepared for impact testing. In order to increase plastic constraint of subsize specimen, side-groove was introduced. Results between subsize and full size impact testing were compared. Size effects correlations were developed for the impact properties of turbine rotor material. These correlations successfully predict the ductile brittle transition temperature (DBTT) of full size Charpy impact specimens based on subsize specimen data.

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A Study on the Evaluation of Material Degradation for High Temperature Sturctural Components by Using Grain Boundary Etching method (입계육식법에 의한 고온부재의 경년 열화도 평가에 관한 연구)

  • Yu, Hyo-Seon;Jeong, Se-Hui
    • Korean Journal of Materials Research
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    • v.6 no.3
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    • pp.253-263
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    • 1996
  • 고온.고압하에서 장시간 사용되는 고온부재용 구조물은 경년열화현상을 나타낸다 그러므로 구조물의 안정성 측면에서 재질열화의 정도를 정량적으로 평가하는 것이 중요하다. 그러나 실기 구조물에서 채취할 시험편의 크기와 수는 제한이 되기 때문에 새로운 비파괴적인 평가법이 요구되고 있다. 따라서 본 연구에서는 화력발전설비에 이용되는 탄소강과 페라이트강에 대한 열화도의 평가를 위해 입계부식법의 적용 가능성을 조사한다. 시험결과, 재질열화의 정도는 사용시간보다 사용온도에 더 큰 영향을 받았으며, Larson-Miller인자와 열화도([$\Delta$DBTT]SP)사이의 관계는 선형적이었으나, 강종에 따라 다른 기울기를 보였다. 반면, 연성-취성천이온도 ([$\Delta$DBTT]SP)와 격자절단비(Ni/No)와 관계는 강종에 무관하게 선형적인 비례관계를 나타내었다. 또한, [$\Delta$DBTT]SP와 Ni/No 의 관계로부터 입계부식법은 페라이트계 강뿐만아니라 탄소강에 대해서도 유용한 재질열화 평가 방법임을 알 수 있었다.

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Estimation of fracture toughness of X65 and X70 steels by DWTT (X65 및 X70강 가스배관의 DWTT 및 파괴인성평가)

  • Cho, Ye-Won;Song, Young-Ho;Kim, Jeong-Min;Kim, Woo-Sik;Park, Joon-Sik
    • Journal of the Korean Institute of Gas
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    • v.16 no.3
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    • pp.54-64
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    • 2012
  • DWTT (Drop Weigh Tearing Test) is one critical method that can exhibit the fracture properties of line pipe steel, since it estimates the properties with real pipe steel. In this study, the ductile portion, inverse fracture ratio and absorbed energy of API X65 and X70 line pipe steels were estimated with temperature variation. Both steels showed that the ratio of ductile area and absorbed energy were decreased with respect to decreasing the test temperature. However, while the ductile fracture behavior exhibited until $-40^{\circ}C$ for the X70 steel, but it showed until $-30^{\circ}C$ for the X65 steel. The fracture properties were discussed with respect to test temperatures.