• Title/Summary/Keyword: alloy 82/182

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Effect of Hot Forging Ratio on the Mechanical Properties in Incoloy 825 Alloy (Incoloy 825 합금의 기계적 성질에 미치는 열간단조비의 영향)

  • Park, Y.T.;Jeong, Y.H.;Kang, C.Y.
    • Journal of the Korean Society for Heat Treatment
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    • v.29 no.6
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    • pp.259-263
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    • 2016
  • This study was carried out to investigate the effect of hot forging ratio on the microstructure and mechanical properties of incoloy 825 alloy. Hot forging was carried out at the forging ratio of 0%, 60% and 90% respectively in a range of $900^{\circ}C{\sim}1,140^{\circ}C$ and followed solution treatment was conducted at $1,000^{\circ}C$ for 1 hr. In all the specimens of hot forged of 0%, 60% and 90%, precipitates were not observed. The average grain size of 0% specimen is $82{\mu}m$ and that of 60% and 90% is $56{\mu}m$ and $31{\mu}m$, respectively. The range of grain size in the 0% specimen is uneven in $182{\mu}m$ to $31{\mu}m$, but the grain size of 90% specimen is uniform. With increasing hot forging ratio, the mechanical properties such as tensile strength, elongation, hardness increased and impact toughness increased by grain refinement.

Residual Stress Analysis of the Overlay Weld on the Dissimilar Metal Butt Weld (이종재이종재료 Butt 용접에 대한 Overlay 용접의 잔류응력해석)

  • Kim, Kang-Soo;Lee, Ho-Jin;Lee, Bong-Sang;Jung, In-Chul;Byeon, Jin-Gwi;Park, Kwang-Soo
    • Proceedings of the KSME Conference
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    • 2008.11a
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    • pp.534-537
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    • 2008
  • In recent years, the dissimilar metal, Alloy 82/182 welds used to connect stainless steel piping and low alloy steel or carbon steel components in nuclear reactor piping system have experienced cracking due to primary water stress corrosion(PWSCC). It is well known that one reason of the cracking is the residual stress by the weld. But, it is difficult to estimate exactly weld residual stress due to many parameters of welding. In this paper, the analysis of 3 FEM models made by ABAQUS Code is performed to estimate exactly the weld residual stress on the dissimilar metal weld. 3 FEM models are Butt model, Repair model and Overlay model and are the plane.strain 2D model. The thermal analysis and the stress analysis are performed on each model and the residual stresses on each model were calculated and compared respectively. Also, the specimen of Butt model was made and the residual stresses were measured by X-Ray method and Hole Drilling Technique. These results were compared with the FEM result of Butt model.

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Weld Residual Stress According to the Ways of Heat Input in the Simulation of Weld Process using Finite Element Analysis (유한요소법을 이용한 용접공정 모사 시 입열 방법에 따른 용접잔류응력의 영향)

  • Yang, Jun-Seog;Park, Chi-Yong;Lee, Kyoung-Soo
    • Proceedings of the KSME Conference
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    • 2008.11a
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    • pp.98-103
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    • 2008
  • This paper is to discuss distribution of welding residual stresses of a ferritic low alloy steel nozzle with dissimilar metal weld using Alloy 82/182. Two dimensional (2D) thermo-mechanical finite element analyses are carried out to simulate multi-pass welding process on the basis of the detailed and fabrication data. On performing the welding analysis generally, the characteristics on the heat input and heat transfer of weld are affected on the weld residual stress analyses. Thermal analyses in the welding heat cycle process is very important process in weld residual stress analyses. Therefore, heat is rapidly input to the weld pass material, using internal volumetric heat generation, at a rate which raises the peak weld metal temperature to $2200^{\circ}C$ and the base metal adjacent to the weld to about $1400^{\circ}C$. These are approximately the temperature that the weld metal and surrounding base materials reach during welding. Also, According to the various ways of appling the weld heat source, the predicted residual stress results are compared with measured axial, hoop and radial through-wall profiles in the heat affected zone of test component. Also, those results are compared with those of full 3-dimensional simulation.

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Effect of preemptive weld overlay on residual stress of repaired weldment in surge nozzle (예방 용접 overlay 가 밀림관 노즐 보수 용접부 잔류응력에 미치는 영향)

  • Oh, Chang-Young;Song, Tae-Kwang;Bae, Hong-Yeol;Chun, Yun-Bae;Kim, Yun-Jae;Lee, Kyoung-Soo;Park, Chi-Yong
    • Proceedings of the KSME Conference
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    • 2008.11a
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    • pp.94-97
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    • 2008
  • In the welding process, weldments usually include repair weld during the manufacturing process. Repair welds is supposed to cause strong tensile residual stress. Moreover weldments, usually made by Alloy 82/182, is susceptible to PWSCC. Therefore, mitigation of welding residual stress in weldments is important for reliable operating. PWOL is one of the methods for mitigation and verified for over twenty years. In this paper, residual stress distribution of repaired weldments and the effect of PWOL on mitigation is examined for surge nozzle.

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Mechanics Evaluations of Stress Corrosion Cracking for Dissimilar Welds in Nuclear Piping System (원자력 배관 이종금속 용접부 웅력부식균열의 역학적 평가)

  • Park, Jun-Su;Na, Bok-Gyun;Kim, In-Yong
    • Proceedings of the KWS Conference
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    • 2005.11a
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    • pp.38-40
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    • 2005
  • Fracture mechanics evaluation of stress corrosion cracking (SCC) in the dissimilar metal weld (DMW) for the nuclear piping system is performed; simulating the transition joint of the ferritic nozzle to austenitic safe-end fabricated with the Inconel Alloy A82/182 buttering and welds. Residual stresses in the DMW are computed by the finite element (FE) analyses Then, to investigate the SCC in the weld root under the combined residual and system operation stresses, the fracture mechanics parameters for a semi-elliptical surface crack are evaluated using the finite element alternating method (FEAM). As a result, it is found that the effect of weld residual stresses on the crack-driving forces is dominant, as high as three times or more than the operation stresses.

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Crack Growth Analysis due to PWSCC in Dissimilar Metal Butt Weld for Reactor Piping Considering Hydrostatic and Normal Operating Conditions (수압시험 및 정상운전 하중을 고려한 원자로 배관 이종금속 맞대기 용접부 응력부식균열 성장 해석)

  • Lee, Hwee-Sueng;Huh, Nam-Su;Lee, Seung-Gun;Park, Heung-Bae;Lee, Sung-Ho
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.37 no.1
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    • pp.47-54
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    • 2013
  • This study investigates the crack growth behavior due to primary water stress corrosion cracking (PWSCC) in the dissimilar metal butt weld of a reactor piping using Alloy 82/182. First, detailed finite element stress analyses were performed to predict the stress distribution of the dissimilar metal butt weld in which the hydrostatic and the normal operating loads as well as the weld residual stresses were considered to evaluate the stress redistribution due to mechanical loadings. Based on the stress distributions along the wall thickness of the dissimilar metal butt weld, the crack growth behavior of the postulated axial and circumferential cracks were predicted, from which the crack growth diagram due to PWSCC was proposed. The present results can be applied to predict the crack growth rate in the dissimilar metal butt weld of reactor piping due to PWSCC.

Effect of Similar Metal Weld & Preemptive Weld Overlay On Residual Stress of Repair Weldment In Surge Nozzle (고리 원전 밀림관 노즐의 동종용접과 예방용접 Overlay가 보수용접 잔류응력에 미치는 영향)

  • Oh, Chang-Young;Song, Tae-Kwang;Shim, Kwang-Bo;Kim, Ji-Soo;Kim, Yun-Jae;Lee, Kyung-Soo
    • Journal of the Computational Structural Engineering Institute of Korea
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    • v.22 no.6
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    • pp.557-564
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    • 2009
  • Welding residual stress is occurred after welding process. Tensile residual stress is one factor of PWSCC. Repair welding usually happened during the manufacturing welding process. Repair welds cause strong tensile residual stress. In PWR, Repair weldments made by Alloy 82/182 is susceptible to PWSCC caused by tensile stress, material and environment. Therefore, mitigation of welding residual stress in weldments is important for reliable operating. PWOL is one of the methods for mitigation and verified for over twenty years. In this paper, residual stress distribution of repaired weldments and the effect of PWOL on mitigation is examined for surge nozzle.

Recovery of Zirconium and Removal of Uranium from Alloy Waste by Chloride Volatilization Method

  • Sato, Nobuaki;Minami, Ryosuke;Fujino, Takeo;Matsuda, Kenji
    • Proceedings of the IEEK Conference
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    • 2001.10a
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    • pp.179-182
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    • 2001
  • The chloride volatilization method for the recovery of zirconium and removal of uranium from zirconium containing metallic wastes formed in spent fuel reprocessing was studied using the simulated alloy waste, i.e. the mixture of Zr foil and UO$_2$/U$_3$O$_{8}$ powder. When the simulated waste was heated to react with chlorine gas at 350- l00$0^{\circ}C$, the zirconium metal changed to volatile ZrCl$_4$showing high volatility ratio (Vzr) of 99%. The amount of volatilized uranium increases at higher temperatures causing lowering of decontamination factor (DF) of uranium. This is thought to be caused by the chlorination of UO$_2$ with ZrCl$_4$vapor. The highest DF value of 12.5 was obtained when the reaction temperature was 35$0^{\circ}C$. Addition of 10 vol.% oxygen gas into chlorine gas was effective for suppressing the volatilization of uranium, while the volatilization ratio of zirconium was decreased to 68% with the addition of 20 vol.% oxygen. In the case of the mixture of Zr foil and U$_3$O$_{8}$, the V value of uranium showed minimum (44%) at 40$0^{\circ}C$ with chlorine gas giving the highest DF value 24.3. When the 10 vol.% oxygen was added to chlorine gas, the V value of zirconium decreased to 82% at $600^{\circ}C$, but almost all the uranium volatilized (Vu=99%), which may be caused by the formation of volatile uranium chlorides under oxidative atmosphere.ere.

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