• 제목/요약/키워드: alloy 690

검색결과 100건 처리시간 0.021초

금속 생체재료를 위한 Sn 함량에 따른 Zr-7Cu 합금설계 (Zr-7Cu Alloy Design According to Sn Content for Bio-Metallic Materials)

  • 김민석;김정석
    • 한국재료학회지
    • /
    • 제31권12호
    • /
    • pp.690-696
    • /
    • 2021
  • The purpose of this study is to develop a zirconium-based alloy with low modulus and magnetic susceptibility to prevent the stress-shielding effect and the generation of artifacts. Zr-7Cu-xSn (x = 1, 5, 10, 15 mass%) alloys are prepared by an arc melting process. Microstructure characterization is performed by microscopy and X-ray diffraction. Mechanical properties are evaluated using micro Vickers hardness and compression test. The magnetic susceptibility is evaluated using a SQUID-VSM. The average magnetic susceptibility value of the Zr-7Cu-xSn alloy is 1.176 × 10-8 cm3g-1. Corrosion tests of zirconium-based alloys are conducted through polarization test. The average Icorr value of the Zr-7Cu-xSn alloy is 0.1912 ㎂/cm2. The elastic modulus value of 14 ~ 18 GPa of the zirconium-based alloy is very similar to the elastic modulus value of 15 ~ 30 GPa of the human bone. Consequently, the Sn added zirconium alloy, Zr-7Cu-xSn, is very interesting and attractive as a biomaterial that reduces the stress-shielding effect caused by differences of elastic modulus between human bone and metallic implants. In addition, this material has the potential to be used in metallic dental implants to effectively eliminate artifacts in MRI images due to low magnetic susceptibility.

Corrosion release behavior of alloy 690 and its application in high-temperature water with Zn injection

  • Liao, Jiapeng;Hu, Yousen;Li, Jinggang;Jin, Desheng;Meng, Shuqi;Ruan, Tianming;Hu, Yisong;Zhang, Ziyu
    • Nuclear Engineering and Technology
    • /
    • 제54권3호
    • /
    • pp.984-990
    • /
    • 2022
  • Corrosion release behavior of Alloy 690 in high-temperature water was investigated under the conditions of injected Zn concentrations of 0 ppb, 10 ppb and 50 ppb. A protective oxide film composed of Zn(FexCr1-x)2O4 and Cr2O3 was formed with Zn injection, resulting in a better corrosion resistance. In comparison with the Zn-free condition, the corrosion release rate under the Zn-injection conditions was smaller. The corrosion release inhibiting factors were 1.7 and 1.9 under the conditions of 10 ppb and 50 ppb Zn-injection respectively. A foreseen application of the corrosion and corrosion release rates has been proposed and discussed.

인코넬 690의 강화기구에 관한 연구 (On the Strengthening mechanisms of INCONEL 690)

  • 허무영;박용수;안성욱
    • 소성∙가공
    • /
    • 제6권3호
    • /
    • pp.213-220
    • /
    • 1997
  • The microstructure of the inconel 690 alloy was varied by the solution treatment and the thermal treatment. The specimens having different microstructures were examined in order to understand the strengthening mechanism of the inconel 690. The level of supersaturation of carbon in the solid solution was increased by applying a longer solution treatment at 115$0^{\circ}C$. As increased carbon content in the solid solution, more carbides precipitated during the thermal treatment at $700^{\circ}C$. Since the carbides played a role of obstacle on the movement of dislocations, a higher tensile strength was obtained in the sample having a large number of carbider. The accumulation of dislocations at the grain boundary carbides caused the development of intergranular fracture which led to a lower elongation.

  • PDF

원자력발전 설비의 소재와 용접방법에 대한 최신 기술동향 (Recent study of materials and welding methods for nuclear power plant)

  • 유호천
    • Journal of Welding and Joining
    • /
    • 제33권1호
    • /
    • pp.14-23
    • /
    • 2015
  • Recent developing tendency of nuclear power plant are studied by searching of NDSL, KIPRIS, Science Direct and so on. Welding materials such as low alloyed steels, stainless steels, nickel-based alloys, zirconium alloy and welding methods such as narrow gap welding, laser beam welding, friction stir welding, overlay welding are investigated.

인코넬 합금의 절삭특성에 관한 연구 (A Study on the Cutting Characteristics of Inconel 690 alloy)

  • 황경충
    • 한국공작기계학회:학술대회논문집
    • /
    • 한국공작기계학회 1999년도 추계학술대회 논문집 - 한국공작기계학회
    • /
    • pp.315-319
    • /
    • 1999
  • This paper has been considered on the cutting characteristics such as chip formation and surface roughness for Inconel 690 alloy with difficult-to-cut because of high toughness and strength. We have made efforts solving the problem to difficult-to-cut of Inconel by improvement of tool with TiN coating and the selection of optimum cutting condition. We used the CCD camera and the surface roughness tester to observe the chip formation and the state of machined surface by using the improved tool with diamond coating and various cutting condions. We have found that the chip formation showed the tooth shape of tooth blade and the surface roughness was very poor. but it can be better by selection of optimum cutting condition.

  • PDF

Alloy 690 제1열 시제전열관의 U 굽힘가공에서 치수평가 및 표면잔류응력

  • 김우곤;이창규;장진성;국일현;이동희;주영한
    • 한국원자력학회:학술대회논문집
    • /
    • 한국원자력학회 1997년도 춘계학술발표회논문집(2)
    • /
    • pp.110-117
    • /
    • 1997
  • Alloy 690 제1열 시제 전열관을 U 굽힘 가공할 시 전열관에 도입된 표면 잔류응력 및 굽힘 단면에서 치수변화 (벽두께, 진원도)를 위치별로 측정하여 평가하였다. 외측호(extrados)의 표면 잔류응력은 $\psi$=0$^{\circ}$에서 축 방향 응력이 -319 MPa (압축)로 가장 높았으며, 내측호(intrados)는 $\psi$=0$^{\circ}$, 160$^{\circ}$ 위치인 천이영역 부관에서 응력 변화가 크게 되는 경향을 보였다 측면(flank)은 인장 잔류응력으로 $\psi$=90$^{\circ}$(apex)에서 최대 190 MPa 로 축방향 응력으로 나타났다. 잔류응력치는 벽두께 보다는 진원도 변화와 일치되어 나타났으며, 시제 전열관의 벽두께 및 진원도는 ASTM의 치수 허용치 내에 포함되는 것으로 평가되었다. 잔류응력 측정은 스트레인 게이지를 이용한 구멍뚫기 방법 (Hole-Drilling Method)을 사용하였다.

  • PDF

Alloy 690에서 용체화처리에따른 미세조직 관찰

  • 이용복;이덕열;장진성;국일현
    • 한국원자력학회:학술대회논문집
    • /
    • 한국원자력학회 1996년도 추계학술발표회논문집(2)
    • /
    • pp.469-474
    • /
    • 1996
  • Alloy 690은 응력부식 균열에 대한 저항성이 요구되는 원자력 발전소 증기발생기 전열관 재료에 사용되고 있다$^{(1)}$ . 응력부식 균열에 대한 저항성은 주로 결정입계에 존재하는 크롬탄화물의 기여에 의한 것이 대부분이다. 크롬탄화 석출물의 핵생성을 알아보기 위해서 110$0^{\circ}C$에서 용체화처리를 0, 1, 3, 10분 동안 하여 관찰하였다. 용체화처리한 모든 시편에서 결정입계에 존재하는 석출물의 분포는 쌍정과 교차하면서 갑자기 변화하는 것을 관찰 할 수 있다. 이처럼 석출물이 존재하지 않는 결정입계들은 대부분 낮은 ∑ 값의 CLS으로부터 약간 벗어난 입계가 될 것이다. 결정입계에 존재하는 석출물은 기지와 Cube-Cube orientation relationship을 갖는다. 그리고 단지 하나의 결정입과 반정합을 이룬다. 기지와 반정합을 이루는 석출물은 M$_{23}$ C$_{6}$형태의 크롬 탄화물이고 격자상수는 기지의 격자상수보다 3배 크다.

  • PDF

Burst pressure estimation of Alloy 690 axial cracked steam generator U-bend tubes using finite element damage analysis

  • Kim, Ji-Seok;Kim, Yun-Jae;Lee, Myeong-Woo;Jeon, Jun-Young;Kim, Jong-Sung
    • Nuclear Engineering and Technology
    • /
    • 제53권2호
    • /
    • pp.666-676
    • /
    • 2021
  • This paper presents numerical estimation of burst pressures of axial cracked U-bend tubes, considering the U-bending process analysis. The validity of the FE simulations is confirmed by comparing with published experimental data. From parametric analyses, it is shown that existing EPRI burst pressure estimation equations for straight tubes can be conservatively used to estimate burst pressures of the U-bend tubes. This is due to the increase in yield strength during the U-bending process. The degree of conservatism would decrease with increasing the bend radius and with increasing the crack depth.