• Title/Summary/Keyword: inconel 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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Corrosion Behavior of Ni 200 and Ni-base Alloys in Hot Lithium Molten salt (고온 리튬용융염에서 Ni 200 및 Ni-base 합금의 부식거동)

  • Cho Soo-Hang;Lim Jong-Ho;Yun Ki-Seok;Park Seung-Won
    • Korean Journal of Materials Research
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    • v.14 no.4
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    • pp.251-259
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    • 2004
  • In the development of the advanced spent fuel management process based on the molten salt technology, it is essential to choose the optimum material for the process equipment handling molten salt. Corrosion behavior of Ni 200 and Ni-base alloys in molten salt of LiCl-$Li_2$O under oxidation atmosphere was investigated in the temperature range of $650~800^{\circ}C$ for 24~312 hrs. The order of corrosion rate was Ni 200 > Inconel 690 > Inconel 601 > Inconel 600. Inconel 600 alloy showed the highest corrosion resistance among the examined alloys, but Ni 200 exhibited the highest corrosion rate. Corrosion products of Inconel 600 and Inconel 601 were $Cr_2$$O_3$ and $NiFe_2$$O_4$. In case of Inconel 690, a single layer of $CrO_2$$O_3$ was formed in the early stage of corrosion and an outer layer of $NiFe_2$O$_4$ and inner layer of $Cr_2$$O_3$ were formed with increase of corrosion time. Inconel 600 showed local corrosion behavior and Inconel 601, 690 showed uniform corrosion behavior.

Experimental studies on the fretting wear of domestic steam generator tubes (국내 증기발생기 전열관 마열에 대한 실험적 연구)

  • Lee, Yeong-Ho;Kim, Hyeong-Gyu;Kim, In-Seop
    • Proceedings of the Korean Society of Tribologists and Lubrication Engineers Conference
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    • 2002.05a
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    • pp.304-309
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    • 2002
  • Fretting wear test in room temperature water was performed to evaluate the wear coefficient of Inconel 600,690 (Pressurized Water Reactor, PWR) and Alloy 800 (CANadian DeuteriumUranium, CANDU) steam generator (SG) tubes against ferritic and martensitic stainless steels. The main focus is to compare the wear behaviors between Alloy 800 and Inconel alloys. Test conditions are $10{\sim}30N$ of normal load, $200{\sim}450{\mu}m$ of sliding amplitude and 30Hz of frequency. The result indicated that the wear rate of Alloy 800 was higher than those of Inconel 690 at various test condition such as normal loads, sliding amplitudes etc. From the results of SEM observation, there was little evidence of plastic deformation layer that were dominantly formed on the worn surfaces of Inconel 690. Also, wear particles in Alloy 800 were released from contacting asperities deformed by severe plastic flow during fretting wear. Main cause of wear rate between Alloy 800 and Inconel 690 may be due to the difference of hardness between martensitic and ferritic stainless steel. The wear rate and wear mechanism of two tubes in room temperature water are discussed.

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Fretting Wear and Friction of lnconel 690 for Steam Generator Tube in Elevated Temperature Water

  • Lee, Young-Ze;Lim, Min-Kyu;Oh, Se-Doo
    • KSTLE International Journal
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    • v.3 no.1
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    • pp.49-53
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    • 2002
  • Inconel 690 for nuclear steam generator tube has more chromium than the conventionally used Inconel 600 in order to increase the corrosion resistance. TD evaluate the tribological characteristics under fretting condition the fretting tests as well as sliding tests were carried out in elevated temperature water environment. 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. Also, the conventional sliding tests of pin-en-disk type were carried out to compare the test results. In fretting, the friction was very sensitive to the load and the amplitude. The friction coefficient decreased with increasing load and decreasing amplitude. Also, the wear of Inconel 690 can be predictable using the work rate model. Depending on normal loads and vibrating amplitudes, distinctively different wear mechanisms and of ten drastically different wear rates can occur. It was fecund that the fretting wear coefficients in water were increased as increasing the temperature of water.

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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Effects of Microstructure on the Fretting Wear of Inconel 690 Steam Generator Tube

  • Hong, Jin-Ki;Kim, In-Sup;Park, Chi-Yong;Kim, Jin-Weon
    • Nuclear Engineering and Technology
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    • v.34 no.2
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    • pp.132-141
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    • 2002
  • The effects of microstructure on fretting wear were investigated in Inconel 690 tube. The microstructure observation indicated that the solution annealing temperature and time affected the grain size of the Inconel 690 tubes. The carbide morphology, along grain boundaries, was mainly affected by thermal treatment time and temperature. The wear test results showed that specimens with larger grain size and with coarse carbides along grain boundaries had better wear resistance. Cracks were found in specimens with carbides along the grain boundary, while few cracks were found in carbide free specimens. It seemed that the carbides on grain boundary assisted crack formation and propagation in carbide containing specimens. On the other hand, the micro-hardness of specimen did not have a major role in fretting wear. It could be inferred from the SEM images of worn surfaces that the main wear mechanism of carbide containing specimen was delamination, while that of carbide free specimen was abrasion.