• Title/Summary/Keyword: 인코넬-690

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Deformation and Recrystallization of INCONEL 690 (인코넬 690의 변형 및 재결정)

  • 표은종;허무영
    • Proceedings of the Korean Society for Technology of Plasticity Conference
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    • 1995.10a
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    • pp.167-171
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    • 1995
  • The formation of preferred orientations in cold rolled and recrystallized Inconel 690 sheets was studied by the x-ray texture measurements and TEM observations. The increasing{220} pole intensity in the plane normal at the higher reductions was related to the{110}<112> texture component. The rolling texture of the Inconel 690 was the pure metal type. THe dislocation cells were found in the near{110}<112> oriented grains. The onset of deformation twins in the {112}<111>oriented grains. The onset of deformation twins in the {112}<111> oriented grains. The onset of deformation twins in the {112}<111> oriented grains caused the weakening of {112}<111> and the development of {552}<115> in the rolling texture. The annealing texture of the Inconel 690 sheets was dependent on the annealing temperature. The annealing texture of 750$^{\circ}C$ annealed sheets was similar to the cold rolling texture. The major preferred orientations of the 950$^{\circ}C$ annealed specimens were {112}<110> and {001}<110>. The formation of fine and closely spaced annealing twins in the specimen annealed at 1150$^{\circ}C$ led to the randomization of the annealing texture.

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

  • 허무영;박용수;안성욱
    • Transactions of Materials Processing
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    • v.6 no.3
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    • pp.213-220
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    • 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.

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Development of Microstructure and Texture in Cold Rolled INCONEL690 (냉간압연된 인코넬 690에서 미세조직과 집합조직의 발달)

  • 안재평;표은종;허무영
    • Transactions of Materials Processing
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    • v.3 no.4
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    • pp.392-400
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    • 1994
  • The formation of preferred orientations in the cold rolling texture of the Inconel 690 sheets was studied by the x-ray texture measurements and TEM observations. The increasing {220} pole intensity in the plane normal at the higher reductions was related to the {110}<112> texture component. The rolling texture of the Inconel 690 was the pure metal type which could be described by {112}<111>, {123}<634> and {110}<112> orientations. The dislocation cells were found in the near {110}<112> oriented grains. The onset of deformation twins in the {112}<111> oriented grains caused the weakening of {112}<111> and the development of {552}<115> in the rolling texture.

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증기발생기 건전성관련 고온관의 적정온도 설정을 위한 분석

  • 민경성;한규성;박순희
    • Proceedings of the Korean Nuclear Society Conference
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    • 1995.10a
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    • pp.437-443
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    • 1995
  • 국내, 외에서 원자력발전소의 주요 구성 기기인 증기발생기의 세관 건전성과 관련 설계개선을 위한 연구가 활발히 진행되고 있다[2,3,4,5,6]. 현재 가동중인 발전소에서는 개선된 증기발생기로 교체하고자 하는 검토가 이루어지고 있으며, 설계중인 발전소에서는 중기발생기의 건전성을 향상시키기 위한 노력이 진행되고 있다. 본 논문에서 기존에 조사되고 검토된 자료를 바탕으로 [2] 현재까지 주로 사용되어온 증기발생기의 세관 재질을 인코넬 600 MA(mill annealed)로 사용할 때 40년 수명동안 증기발생기의 건전성을 보장할 수 있는 고온관의 온도를 분석한 결과 적절한 온도가 607$^{\circ}$F(319.4$^{\circ}C$)임을 알았다. 그리고 이 온도를 반영할 때 계통설계에 영향을 주는 설계사항에 대하여 검토하였고, 추가로 인코넬 600 MA보다 고온조건에서 건전성이 양호한 인코넬 690 TT(thermal treatment)를 사용할 때 설계에 미치는 영향도 검토하였다. 이러한 분석결과는 추후 국내 원자력발전소에서 보다 증기발생기의 건전성을 보장하기 위해 설계개선을 하고자 할 때 기초 자료가 되리라 판단한다.

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The Design Optimization of Preventive Measure Against APR1400 Steam Generator Tube Fretting Wear (신형경수로 증기발생기 마모손상 억제를 위한 설계최적화)

  • Lim, Hyuk-Soon;Park, Young-Sheop;Lee, Kwang-Han;Lee, Seok-Ho;Chung, Dae-Yul
    • Proceedings of the KSME Conference
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    • 2004.04a
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    • pp.2047-2052
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    • 2004
  • Inconel-600 alloy has been used as steam generator tube material for current pressurized water reactors (PWRs). The long-term operation of steam generators showed that the use of this material induced localized corrosion damages and increased tube wear of steam generator. To protect these problems, steam generator tube material is being changed to Inconel-690 alloy. Based on the current trend, we have chosen Inconel 690 as the Advanced Power Reactor 1400 (APR1400) steam generator(SG) tube material and performed the design optimization of preventive measure against tube fretting wear for the APR1400 steam generator. In this paper, we examined the technical consideration in this modification : the selection of material, wear characteristics, effect of the Egg-crate Flow Distribution Plate installation, and effect analysis of vertical strip installation.

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Qualitative Analysis of the Component Materials of Nuclear Power Plant Using Time-Resolved Laser Induced Breakdown Spectroscopy (시간분해 레이저 유도 파열 분광분석에 의한 원자력발전소 계통재질의 성분 정성분석)

  • Chung, Kun-Ho;Cho, Yeong-Hyun;Lee, Wanno;Choi, Geun-Sik;Lee, Chang-Woo
    • Analytical Science and Technology
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    • v.17 no.5
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    • pp.416-422
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    • 2004
  • Time-resolved laser induced breakdown spectroscopy (TRELIBS) has been developed and applied to the qualitative analysis of the component materials of nuclear power plant. The alloy samples used in this work were carbon steels (A106 Gr. B; A336 P11; A335 P22), stainless steels (type 304; type 316) and inconel alloys (Inconel 600; Inconel 690; Inconel 800). Carbon steels can be individually distinguished by the intensity ratio of chromium to iron and molybdenum to iron emission lines observed at the wavelength raging from 485 to 575 nm. Type 316 stainless steel can be easily differentiated from type 304 by identification of the molybdenum emission lines at an emission wavelength ranging from 485 to 575 nm: type 304 does not give any molybdenum emission lines, but type 316 does. The inconel alloys can be individually distinguished by the intensity ratio of Cr/Fe and Ni/Fe emission lines at the wavelength raging from 420 to 510 nm. TRELIBS has been proved to be a powerful analytical technique for direct analysis of alloys due to its non-destructivity and simplicity.

Experimental Study for Fretting Wear Characteristics of Inconel 690 Tube (인코넬 690 튜브의 프레팅 마모에 관한 실험적 연구)

  • Kim, Do-Hyung;Kim, Woo-Seok;Bae, Yong-Tak;Hwang, Pyung;Chai, Young-Suk
    • Proceedings of the Korean Society of Tribologists and Lubrication Engineers Conference
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    • 1999.11a
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    • pp.78-83
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    • 1999
  • Fretting Wear Behavior and Characteristics were investigated with Inconel 690 tube which is used in Nuclear Power Plant. Fretting Wear Tester has been engaged in the study of characteristics on tube fretted induced to various factors, i.e. vibration amplitude, contact type, material properties load support geometry, environmental effect Test has been performed in air and at room temperature. Wear volume rate has been approximately estimated as a function of normal load.

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Effect of Cooling Rates on Mechanical Properties and Microstructure of Inconel Alloys (인코넬 합금의 미세조직과 기계적 특성에 미치는 냉각속도 영향)

  • Park, No-Kyeong;Lee, Ho-Seong;Chai, Young-Suck
    • Korean Journal of Materials Research
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    • v.17 no.10
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    • pp.555-559
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    • 2007
  • The mechanical properties and microstructure of Inconel 690 and 600 alloys with various cooling rates were investigated. Optical microscopy and scanning electron microscopy observations indicated that in case of the cooling rate of $0.5^{\circ}C/min$, discontinuous carbides along the grain boundaries were formed and when the cooling rate was $10^{\circ}C/min$, continuous carbides were formed in Inconel 690 and 600 alloys. For the annealed Inconel 690 alloy with high Cr content, a lot of annealing twins, which led the preferential growth of (111) planes, were observed. However, the annealed Inconel 600 alloy with low Cr content showed a few annealing twins and the preferential growth of (200) planes. Inconel 600 alloy had a larger value of ultimate tensile strength (UTS) than Inconel 690 alloy.

Friction and Wear of Inconel 690 for Steam Generator Tube in Fretting (증기발생기 세관용 Inconel 690 의 프레팅 마찰 및 마멸특성)

  • Lee, Young-Ze;Lim, Min-Kyu;Oh, Se-Doo
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.27 no.3
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    • pp.432-439
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    • 2003
  • Inconel 690 for nuclear steam generator tube has more Chromium than the conventionally used Inconel 600 in order to increase the corrosion resistance. To evaluate the tribological characteristics of Inconel 690 under fretting condition the fretting tests were carried out in air and elevated temperature water. Fretting tests of the cross-cylinder type were done under various vibrating amplitudes and applied normal loads in order to measure the friction forces and wear volumes. From the results of fretting wear tests. the wear of Inconel 690 can be predictable using the work rate model. The amounts of friction forces were proportional to relative movement between two fretting surfaces. The friction coefficients were decreased as increasing the normal loads and deceasing the vibrating amplitudes. Depending on fretting environment, distinctively different wear mechanisms and often drastically different wear rates can occur It was found that the fretting wearfactors in air and water at 2$0^{\circ}C$, 5$0^{\circ}C$, and 8$0^{\circ}C$ were 7.38 $\times$ $10^{-13}$$Pa^{-1}$, 2.12 $\times$$10^{-13}$$Pa^{-1}$, 3.34$\times$$10^{-13}$$Pa^{-1}$and 5.21$\times$$10^{-13}$$Pa^{-1}$, respectively flexibility to model response data with multiple local extreme. In this study, metamodeling techniques are adopted to carry out the shape optimization of a funnel of Cathode Ray Tube, which finds the shape minimizing the local maximum principal stress. Optimum designs using two metamodels are compared and proper metamodel is recommended based on this research.

칼리머 노내 상부구조물 하단부의 열 스트라이핑 분석

  • Kim, Jong-Beom;Lee, Hyeong-Yeon;Yoo, Bong
    • Proceedings of the Korean Nuclear Society Conference
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    • 1996.11b
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    • pp.690-696
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    • 1996
  • 본 논문에서는 칼리머 액체금속로의 노내 상부구조 하단부에 발생하는 열 스트라이핑을 해석할 수 있는 단순방법을 제안하였고 또한 인코넬 718 강으로 만든 라이너를 적용하여 노내 상부구조하부에 발생하는 열 스트라이핑 문제를 해소하거나 줄이기 위한 방안을 제시하였다. 해석의 결과 현재 예비설계된 칼리머 노내 상부구조 하단부는 스트라이핑 하중으로부터 건전함을 예측할 수 있었다.

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