• 제목/요약/키워드: Mod.9Cr-1Mo steel

검색결과 16건 처리시간 0.026초

Mod. 9Cr1Mo 강의 크리프 강도에 미치는 경도의 영향 (Effects of hardness values on the creep rupture strength in a Mod. 9Cr1Mo Steel)

  • 이연수;유석현;공병욱;김정태
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2003년도 춘계학술대회
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    • pp.637-642
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    • 2003
  • The Modified 9Cr-1Mo steel identified as T91, P91 and F91 in the ASME specification has been widely used for the construction of modern power plants. The available data on the influence of process parameters during manufacturing and fabrication on its properties are not sufficient. In this study, the influence of various thermal cycles on the hardness and the creep rupture strength was analyzed in the base metal and the weldments made in tube and pipe of a Mod.9Cr-1Mo steel. The low hardness, 155Hv, showed low creep rupture strength below the allowable stresses of T91 base metal in the ASME specification. This low value was attributed to the fully recovered dislocation structure and the weakening of precipitation hardening associated with the abnormal thermal cycles.

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원자력용 개량 9Cr-1Mo 및 9Cr-0.5Mo-2W 강의 미세조직과 기계적 특성 연구 (A Study on Microstructure and Mechanical Properties of Modified 9Cr-1Mo and 9Cr-0.5Mo-2W Steels for nuclear Power Plant)

  • 김성호;송병준;한창석;국일현;류우석
    • 한국재료학회지
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    • 제9권11호
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    • pp.1137-1143
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    • 1999
  • 액체금속로 전열관재료용 개량 9Cr-1Mo강의 특성에 미치는 텅스텐의 영향을 고찰하기 위하여 개량 9Cr-1Mo강에 텅스텐을 2wt.% 첨가하여 템퍼링 온도에 따른 기계적 특성 및 미세조직의 변화를 조사하였다. 미세조직을 관찰한 결과 템퍼링시 전위회복에 의해 형성되는 셀 구조가 나타나는 템퍼링 온도는 개량 9Cr-1Mo강의 경우 $700^{\circ}C$인 반면, 텅스텐을 첨가한 9Cr-0.5Mo-2W강의 경우는 $750^{\circ}C$이었으며, 이 결과로부터 텅스텐 첨가는 전위회복을 지연하였음을 알 수 있다. 텅스텐을 첨가하여도 템퍼링 온도에 따라 생성되는 석출물의 종류는 차이가 없었으나, 텅스텐을 첨가한 강에 있는 석출물에는 텅스텐이 포함되어 있었다. 텅스텐의 첨가로 경도값, 고온 인장강도 그리고 항복강도가 증가하였다. 이것은 텅스텐 첨가로 인한 미세구조의 안정화에 기인하는 것으로 보인다. 충격시험에서는 항복강도가 낮은 개량 9Cr-1Mo강이 더 우수한 충격파괴특성을 가졌다.

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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.

Modified 9Cr-1Mo 강의 열화도 평가 (The Evaluation of Materials Degradation in Modified 9Cr-1Mo Steel)

  • 현양기;이재도
    • 연구논문집
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    • 통권31호
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    • pp.157-163
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    • 2001
  • Evolution of microstructure due to service exposure to high temperature has a strong effect performance of heat resistant steels. In case of modified 9Cr-1Mo steels, precipitation of $Fe_2Mo$-type laves phases and coarcening of $M_23C_6$-type carbides is the primary cause of degradation of mechanical properties such as creep resistance, tensile strength and toughness. Creep tests have been carried out on pre-aging mod. 9Cr-1Mo steels to examine the effect of pre-aging and stress on the creep strength. Based on the results, a nondestructive procedure, where electrochemical technique that quantitatively detect laves phases and $M_23C_6$-type carbides in a material is used, has been proposed to evaluate a residual creep life of mod. 9Cr-1Mo steels.

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개량 9Cr-1Mo 강의 장시간 크리프거동에 미치는 경도와 하부조직의 영향 (Effect of Hardness and Substructure on Long-term Creep Behavior of Mod.9Cr-1Mo Steel)

  • 박규섭;이근진;정한식;김정호;정영관;엔도타카오
    • 한국정밀공학회지
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    • 제21권2호
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    • pp.168-176
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    • 2004
  • Interrupted creep tests were carried out on the Mod.9Cr-1Mo steel in order to investigate the structural degradation during creep. The ranges of creep stress and temperature were from 71 to 167MPa and 873 to 923k, respectively. The change of hardness and tempered martensitic lath width were measured in the grip and gauge parts of interrupted specimens. The lath structure was thermally stable in static conditions, but was not stable during creep, and the structural evolution was enhanced by creep strain. The relation between the change in lath width and strain was described in the from, $\delta$W= a ($W_s-W_o$)$cdot;varepsilon$, where $\varepsilon$ is the strain, $W_o$is the initial lath width, $W_s$ is the final lath width depending solely on stress, and a is the constant of the magnitude of 0.67 $\mu$m /strain. The change in Victors hardness was expressed by a one-valued function of creep life consumption ratio. Based on the empirical relation between strain and lath width, a model was proposed to explain the relation between change in hardness and creep life consumption ratio. The model revealed that about 65$%$ of dislocations in lath structures were eliminated by the migration of subboundaries.

고온 원자로용 Mod. 9Cr-1Mo강 후판재의 깊이에 따른 미세조직 및 기계적 특성 변화 (Through Thickness Microstructure and Mechanical Properties in a Forged Thick Section Mod. 9Cr-1Mo Steel)

  • 이선희;박상규;김민철;이봉상;김선진
    • 한국압력기기공학회 논문집
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    • 제7권2호
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    • pp.42-47
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    • 2011
  • The purpose of this study is to investigate the effects of through thickness on the mechanical properties and microstructural features in Mod. 9Cr-1Mo steels for RPVs. The microstructures at all locations were typically tempered martensite, but small amount of delta ferrite was observed at the center region. The prior austenite grain size increased with the depth from the surface. The yield strengths of center and 1/4T location were higher than that of surface by 30MPa. The impact toughness of center was low compared to those of other specimens. Also, upper shelf energy was low at the center. The toughness deterioration in center might be caused by larger size of the prior austenite grains and existence of the delta ferrite.

Mod.9Cr-1Mo강의 항온변태시 기계적 특성변화에 미치는 Cr탄화물의 영향 (Influence of the Cr-Carbides on the Mechanical Characteristics during Isothermal Heat-Treatment of the Mod.9Cr-1Mo Steel)

  • 허성강;이재현;구지호;신기삼;;신종호
    • 한국재료학회지
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    • 제22권1호
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    • pp.46-53
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    • 2012
  • In this study, mechanical tests and microstructural analyses including TEM analyses with EDX of precipitates in modified 9Cr-1Mo steel were carried out to determine the cause of embrittlement observed after heat-treatment, which limits the usage of the alloy for power plants. Mod. 9Cr-1Mo steel specimens at austenite temperature were quenched to the molten salt baths at $760^{\circ}C$ and $700^{\circ}C$, in which the specimens were kept for 10 min ~ 10 hr with subsequent air-cooling. Impact tests showed that the impact value dropped abruptly when the specimens were kept longer than 30 min at $\sim760^{\circ}C$ reaching to minima in about 1 hr, and then increasing at further retention. The tensile strength of the specimens reached the minimum value without much change afterward, whereas the values of elongation showed the same trend as that of the impact value. The isothermally heat-treated steel at $700^{\circ}C$ also showed a minimum impact value in about 1 hr. These results suggest that the isothermal heattreatment at 760 and $700^{\circ}C$ for about 1 hr induces temporal embrittlement in Mod. 9Cr-1Mo steel. The microstructural examination of all the specimens with extraction replica of the carbides revealed that the specimens with temporal embrittlement had $Cr_2C$, indicating that the cause of the embrittlement was the precipitation of the $Cr_2C$. In addition, TEM/EDX results showed that the Fe/Cr ratio was 0.033 to 0.055 for $Cr_2C$, whereas it was 0.48 to 0.75 for $Cr_{23}C_6$, making the distinction of the $Cr_2C$ and $Cr_{23}C_6$ possible even without direct electron diffraction analyses.

Mod. 9Cr-1Mo강에서의 $550^{\circ}C$ 부근에서 템퍼링시 발생하는 취성에 관한 연구 (Study on the Embrittlement of the Mod. 9Cr-1Mo Steel Tempered at $550^{\circ}C$)

  • 구지호;신종호;허성강
    • 열처리공학회지
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    • 제23권3호
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    • pp.156-162
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    • 2010
  • The modified 9Cr-1Mo steel (P91 steel) is very popular as a boiler tube material of the USC (Ultra-Supercritical) power plants. The steels were tempered in the temperature range of 400 to $650^{\circ}C$ and the mechanical tests, such as impact and hardness tersts were performed at the room temperature for the tempered steels. A drop in the impact value (embrittlement) and the hardeness increase were simultanously observed in the range of temperature between $475^{\circ}C$ and $600^{\circ}C$, particularly at $550^{\circ}C$. TEM observation shows the hardening was caused by $M_2C$, resulting in the embrittlement. And the maximum volume fraction of $M_3C$ was also observed at $550^{\circ}C$, Therefore, the embrittlement seems to be caused by both the $M_2C$ and $M_3C$.

열시효가 Mod.9Cr-1Mo강의 재료강도 및 파괴 거동에 미치는 영향 (Effect of Thermal Aging on Material Strength and Fracture Behavior in Mod.9Cr-1Mo Steel)

  • 이형연;김우곤;손석권;홍석우;석창성
    • 대한기계학회논문집 C: 기술과 교육
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    • 제4권2호
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    • pp.101-109
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    • 2016
  • 발전소 내열강의 물성치는 고온 가동시간이 누적됨에 따라 열시효의 영향을 받는다. 본 연구에서는 제 4 세대 원자력시스템의 재료로 널리 채택되고 있는 Mod.9Cr-1Mo (ASME Grade 91)강을 대상으로 항복강도, 인장강도 및 파괴거동에 열시효가 미치는 영향에 대해 조사 및 분석하였다. 국내에서 가동 중인 초초임계(USC) 화력발전소의 배관계통에서 채취한, 73,716 시간의 가동 이력을 겪은 Gr.91 강 재료가 재료 실험을 위해 사용되었고, 동 시험결과와 가동 이력을 겪지 않은 신재의 시험결과를 비교 분석하였다. 또한 ASME 코드의 물성치와 RCC-MRx 의 물성치와 비교 분석하였고, 이들 설계기술기준 물성치의 보수성은 신재 및 가동 이력을 겪은 재료의 시험결과와 비교 분석을 통해 정량화하였다.