• Title/Summary/Keyword: alloy 600

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Formation of Particles in the Laser Melted Zone of Alloy 600

  • Lim, Yun-Soo;Cho, Hai-Dong;Kuk, Il-Hiun;Kim, Joung-Soo
    • Proceedings of the Korean Nuclear Society Conference
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    • 1997.05b
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    • pp.80-85
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    • 1997
  • Studies on particles formed in the laser melted zone (LMZ) of sensitized Ni base Alloy 600 have been carried out using microscopic equipments. Most of them were identified as TiN type and MgS type particles were also found in the cell boundaries. All of the particles were located in the cellular solidification region, but no particle was formed in the plane front solidification regions of the LMZ. Cr carbides which had formed during sensitization treatment were completely melted during laser surface melting and hardly re-precipitated during the matrix solidification.

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레이저 표면합금화에 의한 Alloy 600의 미세조직 변화와 내부식성 향상

  • 신진국;강석중;우선기;이홍로;서정훈;김정수
    • Proceedings of the Korean Nuclear Society Conference
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    • 1997.05b
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    • pp.98-103
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    • 1997
  • 원전 증기 발생기 재료로 사용되는 Alloy 600의 내부식성 향상을 위하여 레이저 범을 이용한 레이저 표면합금화(Laser Surface Alloying, LSA) 방법을 이용, 표면에 약 200$\mu\textrm{m}$ 두께의 합금층을 형성시켰다. 첨가한 원소는 크롬 또는 크롬과 니켈의 혼합체를 사용하였으며 첨가법으로는 도금과 용사를 이용하였다. 용사법으로 만든 LSA 시편의 특성과 문제점에 대해 고찰하고 이러한 문제점을 해결하는 방법으로 크롬 도금법을 택하였다. 이들 결과를 레이저 처리를 하지 않은 시편들과 비교하여 부식 거동을 분석하였다. 분석 결과 LSA 시편의 경우 As-received 시편, 레이저 표면 용융(LSM) 들과 비교해 아주 우수한 내부식성을 가졌으며 입계 내부식성도 크게 증가하였다. 이는 크롬 첨가로 인해 크롬의 농도가 많아져 부동태 피막의 형성이 쉬워졌기 때문으로 해석되었다.

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CONSIDERATIONS FOR METALLOGRAPHIC OBSERVATION OF INTERGRANULAR ATTACK IN ALLOY 600 STEAM GENERATOR TUBES

  • HUR, DO HAENG;CHOI, MYUNG SIK;LEE, DEOK HYUN;HAN, JUNG HO
    • Nuclear Engineering and Technology
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    • v.47 no.7
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    • pp.934-938
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    • 2015
  • This technical note provides some considerations for the metallographic observation of intergranular attack (IGA) in Alloy 600 steam generator tubes. The IGA region was crazed along the grain boundaries through a deformation by an applied stress. The direction and extent of the crazing depended on those of the applied stress. It was found that an IGA defect can be misevaluated as a stress corrosion crack. Therefore, special caution should be taken during the destructive examination of the pulled-out tubes from operating steam generators.

Effect of oxide film on ECT detectability of surface IGSCC in laboratory-degraded alloy 600 steam generator tubing

  • Lee, Tae Hyun;Ryu, Kyung Ha;Kim, Hong Deok;Hwang, Il Soon;Kim, Ji Hyun;Lee, Min Ho;Choi, Sungyeol
    • Nuclear Engineering and Technology
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    • v.51 no.5
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    • pp.1381-1389
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    • 2019
  • Stress corrosion cracking (SCC) widely found in both primary and secondary sides of steam generator (SG) tubing in pressurized water reactors (PWR) has become an important safety issue. Using eddy-current tests (ECTs), non-destructive evaluations are performed for the integrity management of SG tubes against intergranular SCC. To enhance the reliability of ECT, this study investigates the effects of oxide films on ECT's detection capabilities for SCC in laboratory-degraded SG tubing in high temperature and high pressure aqueous environment.

Effects of Annealing Heat Treatment Conditions on Phase Transformation of Nitinol Shape Memory Alloy (어닐링 열처리 조건에 따른 NITINOL형상기억합금의 상변환 특성 연구)

  • Yoon Sung Ho;Yeo Dong Jin
    • Composites Research
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    • v.18 no.2
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    • pp.38-45
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    • 2005
  • Phase transformation behaviors and crystal structures of Nitinol shape memory alloy $(54.5Ni-45.5Tiwt\%)$ are investigated by varying annealing heat treatment conditions through DSC (Differential Scanning Calorimetry) and XRD (X-Ray Diffraction). Annealing heat treatment conditions were considered as heat treated times of 5min, 15min. 30m1n, and 45min, as well as heat treated temperatures of $400^{\circ}C,\;500^{\circ}C,\;525^{\circ}C,\;550^{\circ}C,\;575^{\circ}C,\;600^{\circ}C,\;700^{\circ}C,\;800^{\circ}C,\;and\;900^{\circ}C$ According to the results, annealing heat treatment conditions such as heat treated times and heat treated temperatures were found to affect significantly on phase transformation behaviors and crystal structures of Nitinol shape memory alloy.

Process Development of Laser Cladding for Weld Inlay Repair of Dissimilar Metal Weld in Reactor Vessel In/Outlet Nozzles (원자로 입출구 노즐 이종금속 용접부 Weld Inlay 레이저 클래딩 공정 개발)

  • Cho, Hong Seok;Jung, Kwang Woon;Mo, Min Hwan;Cho, Ki Hyun;Choi, Dong Chul;Lee, Jang Wook;Cho, Sang Beum
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.11 no.1
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    • pp.53-60
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    • 2015
  • This study was investigated to develop process technology of laser cladding with austenite stainless steel for Weld Inlay repair of dissimilar metal weld in reactor vessel in/outlet nozzles. Weld Inlay experiments were performed by laser cladding repair system consisting of common manipulator, laser apparatus and welding process scheduler, etc. Single pass welding experiments were conducted in order to obtain the optimum welding process parameters for filler wires of ER309L and Alloy 52M before multi-layer laser cladding. Based on the above obtained results, multi-layer laser cladding experiments were carried out, and welding qualities for weld specimens were estimated by PT, OM, SEM and EDS analysis. Consequently, it was revealed that multi-layer laser cladding on austenite stainless steel using filler wires of ER309L and Alloy 52M could be possible to meet ASME Code standard without any weld defect.

Detection of SCC by Electrochemical Noise and In-Situ 3-D Microscopy

  • Xia, Da-Hai;Behnamian, Yashar;Luo, Jing-Li;Klimas, Stan
    • Corrosion Science and Technology
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    • v.16 no.4
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    • pp.194-200
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    • 2017
  • Stress-corrosion cracking (SCC) of alloy 600 and alloy 800 in 0.5 mol/L thiosulfate solution during constant strain was investigated using electrochemical noise (EN) combined with 3-D microscope techniques. The in-situ morphology observation and EN results indicate that the SCC process could be divided into three stages: (1) passive film stabilization and growth, (2) crack initiation, (3) and crack growth. Power Spectral Density (PSD) and the probability distribution obtained from EN were used as the "fingerprint" to distinguish the different processes. During passive film stabilization and growth, the current noise signals resembled "white noise": when the crack initiated, many transient peaks could be seen in the current noise and the wavelet energy at low frequency as well as the noise resistance decreased. After crack propagation, the noise amplitudes increased, particularly the white noises at low and high frequencies ($W_L$ and $W_H$) in the PSDs. Finally, the detection of metal structure corrosion in a simulated sea splash zone and pipeline corrosion in the atmosphere are established.

Edge-Cracking Behavior of CoCrFeMnNi High-Entropy Alloy During Hot Rolling

  • Won, Jong Woo;Kang, Minju;Kwon, Heoun-Jun;Lim, Ka Ram;Seo, Seong Moon;Na, Young Sang
    • Metals and materials international
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    • v.24 no.6
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    • pp.1432-1437
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    • 2018
  • This work investigated edge-cracking behavior of equiatomic CoCrFeMnNi high-entropy alloy during hot rolling at rolling temperatures $500{\leq}T_R{\leq}1000^{\circ}C$. Edge cracks did not form in the material rolled at $500^{\circ}C$, but widened and deepened into the inside of plate as $T_R$ increased from $500^{\circ}C$. Edge cracks were most severe in the material rolled at $1000^{\circ}C$. Mn-Cr-O type non-metallic inclusion and oxidation were identified as major factors that caused edge cracking. The inclusions near edge region acted as preferential sites for crack formation. Connection between inclusion cracks and surface cracks induced edge cracking. Rolling at $T_R{\geq}600^{\circ}C$ generated distinct inclusion cracks whereas they were not serious at $T_R=500^{\circ}C$, so noticeable edge cracks formed at $T_R{\geq}600^{\circ}C$. At $T_R=1000^{\circ}C$, significant oxidation occurred at the crack surface. This accelerated edge crack penetration by embrittling the crack tip, so severe edge cracking occurred at $T_R=1000^{\circ}C$.

Effect of Additives on the Stress Corrosion Cracking Behavior of Alloy 600 in High Temperature Caustic Solutions

  • Hur, Do Haeng;Kim, Joung Soo;Baek, Jae Sun;Kim, Jung Gu
    • Corrosion Science and Technology
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    • v.3 no.1
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    • pp.6-13
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    • 2004
  • The effect of inhibitors on the electrochemical behavior and the stress corrosion cracking resistance of Alloy 600(UNS N06600) was evaluated in 10% sodium hydroxide solution at $315^{\circ}C$. The specimens of a C-ring type for stress corrosion cracking test were polarized at 150 mV above the corrosion potential for 120 hours with and without inhibitors such as titanium oxide, titanium boride and cerium boride. The chemical compositions of the films formed on the crack tip in the C-ring specimens were analyzed using a scanning Auger electron spectroscopy. The cerium boride, the most effective, was observed to decrease the crack propagation rate more than a factor of three compared with that obtained in no inhibitor solution. It was found that the changes of the active-passive transition potentials and the film compositions were related to the resistance to stress corrosion cracking in high temperature caustic solution.

Corrosion of Fe-(8.5~36.9) wt% Cr Alloys at 600~800℃ in (N2, H2S, H2O)-Mixed Gases (Fe-(8.5~36.9) wt% Cr합금의 600~800℃, (N2,H2S,수증기)-혼합 가스분위기에서의 부식)

  • Kim, Min Jung;Lee, Dong Bok
    • Korean Journal of Metals and Materials
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    • v.50 no.3
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    • pp.218-223
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    • 2012
  • Fe-(8.5, 18.5, 28.3, 36.9) wt% Cr alloys were corroded between 600 and $800^{\circ}C$ for up to 70 h in a 1 atm gas mixture that consisted of 0.0242 atm of $H_2S$, 0.031 atm of water vapor, and 0.9448 atm of nitrogen gas. Their corrosion resistance increased with an increment in the Cr content. The Fe-8.5%Cr alloy corroded fast, forming thick, fragile, nonadherent scales that consisted primarily of an outer FeS layer and an inner (Fe, Cr, O, S)-mixed layer. The outer FeS layer grew into the air by the outward diffusion of $Fe^{2+}$ ions, whereas the inner mixed layer grew by the inward diffusion of oxygen and sulfur ions. At the interface of the outer and inner scales, voids developed and cracking occurred. The Fe-(18.5, 28.3, 36.9)% Cr alloys displayed much better corrosion resistance than the Fe-8.5Cr alloy, because thin $Cr_2O_3$ or $Cr_2S_3$ scales formed.