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  • 1
    Electronic Resource
    Electronic Resource
    s.l. ; Stafa-Zurich, Switzerland
    Solid state phenomena Vol. 124-126 (June 2007), p. 1529-1532 
    ISSN: 1662-9779
    Source: Scientific.Net: Materials Science & Technology / Trans Tech Publications Archiv 1984-2008
    Topics: Physics
    Notes: Growth model of a circumferential outer diameter stress corrosion crack (ODSCC) in a retiredsteam generator tube of the Kori 1 nuclear power plant was proposed based on extensive destructiveexaminations of the pulled tubes of Alloy 600 from the Kori 1 plant. A small ODSCC grows in alateral direction as well as a forward direction until it meets a neighboring ODSCC which alsogrows in a lateral direction as well as a forward direction. And then, the two ODSCCs which meeton the same circumferential plane are consolidated into a single ODSCC. By repeating such aconsolidation process with time, it seems that the apparent growth rate of an ODSCC in the lateraldirection is much faster than that in the forward direction. Growth model of a circumferentialODSCC from a retired steam generator tube of the Kori 1 plant reveals that many ODSCCs areinitiated and grow in both directions independently until they meet and finally they are consolidated
    Type of Medium: Electronic Resource
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  • 2
    Electronic Resource
    Electronic Resource
    s.l. ; Stafa-Zurich, Switzerland
    Solid state phenomena Vol. 124-126 (June 2007), p. 1545-1548 
    ISSN: 1662-9779
    Source: Scientific.Net: Materials Science & Technology / Trans Tech Publications Archiv 1984-2008
    Topics: Physics
    Notes: Since the PbSCC(Lead stress corrosion cracking) of alloy 600 tubing materials wasreported by Copson and Dean in 1965, the effect of lead on a corrosion film and crackingmorphology have been continually debated. An electrochemical interaction of lead with thealloying elements of SG tubings was studied and the corrosion products were analyzed. It wasfound that lead enhanced the anodic dissolution of alloy 600 and alloy 690 in the electrochemicaltest. The lead preferentially dissolved the Cr from the corrosion film of alloy 600 and alloy 690 inalkaline water. The lead ion seemed to penetrate into the TG crack tip and react with the corrosionfilm. A selective Cr depletion was observed to weaken the stability of the passive film on the alloys.Whereas passivity of Ni became stable in lead containing solution, Cr and Fe passivity becameunstable
    Type of Medium: Electronic Resource
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  • 3
    Electronic Resource
    Electronic Resource
    s.l. ; Stafa-Zurich, Switzerland
    Advanced materials research Vol. 26-28 (Oct. 2007), p. 1213-1216 
    ISSN: 1662-8985
    Source: Scientific.Net: Materials Science & Technology / Trans Tech Publications Archiv 1984-2008
    Topics: Mechanical Engineering, Materials Science, Production Engineering, Mining and Metallurgy, Traffic Engineering, Precision Mechanics
    Notes: Steam generators(SG) of the Korean nuclear power plants were replaced with a new oneafter a 20 year operation. A metallographic examination of the defected tubes is needed for settingup a guide line for a safe operation of the other SG. A destructive analysis of 50 tubes wasaddressed, and a relationship between the SCC defect location and defect depth wasobtained. Tubes extracted from the retired SG were transferred to a hot laboratory. Detailednondestructive analysis examinations were taken, then the tubes were destructively examined.Types and sizes of the defects were characterized. A location and depth of the SCC were evaluatedin terms of the location and height of the sludge. Most axial cracks were in the sludge pile, whereasthe circumferential ones were around the top of the tube sheet(TTS) or below the TTS. Cracks werefound with various lengths in a specific zone. Average defect depth of the axial cracks was deeperthan that of the circumferential ones
    Type of Medium: Electronic Resource
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  • 4
    Electronic Resource
    Electronic Resource
    s.l. ; Stafa-Zurich, Switzerland
    Key engineering materials Vol. 321-323 (Oct. 2006), p. 666-669 
    ISSN: 1013-9826
    Source: Scientific.Net: Materials Science & Technology / Trans Tech Publications Archiv 1984-2008
    Topics: Mechanical Engineering, Materials Science, Production Engineering, Mining and Metallurgy, Traffic Engineering, Precision Mechanics
    Notes: During the past couple of decades, several limit load solutions have been proposed toresolve steam generator (SG) tube integrity issue. However, for estimation of specific load carryingcapacity under different conditions, these solutions have to be modified by using lots of experimentaldata. The objective of this paper is to introduce a new burst pressure estimation scheme based onfracture mechanics analyses for SG tubes with a crack. In this context, closed-form equations werederived to get relevant parameters from three dimensional elastic-plastic finite element analyses and,then, a series of structural integrity analyses were carried out using the predicted J-integrals from theequations. Finally, in comparison with the experimental data as well as corresponding estimationresults from conventional limit load solutions, it was proven that the proposed estimation scheme canbe used as an efficient tool for integrity evaluation of cracked SG tubes
    Type of Medium: Electronic Resource
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  • 5
    Electronic Resource
    Electronic Resource
    s.l. ; Stafa-Zurich, Switzerland
    Solid state phenomena Vol. 119 (Jan. 2007), p. 87-90 
    ISSN: 1662-9779
    Source: Scientific.Net: Materials Science & Technology / Trans Tech Publications Archiv 1984-2008
    Topics: Physics
    Notes: Alloy 600 tubing can be repaired by using a Ni electroplating to have an excellent SCCresistance. In order to carry out a successful Ni electrodeposition inside a steam generator tubing,the effects of various parameters on the material properties of the electrodeposit should beelucidated. Hence this work deals with the effects of the applied current density and the dutycycle(Ton / (Ton + Toff)) of the pulse current on the material properties of the Ni electrodepositobtained from a Ni sulphamate bath by analyzing the current efficiency, the potentiodynamic curve,the hardness and the stress-strain curve. Hardness, YS(yield strength) and TS(tensile strength)decreased whereas the elongation increased as the applied current density increased. This was dueto a concentration depletion of the nickel ion at the interface of the electrodeposit/solution, and afractional decrease of the hydrogen reduction reaction. As the duty cycle increased, the hardness,YS and TS decreased while the elongation increased. During an off time at a high duty cycle, theconcentration depletion of the nickel ion could not be sufficiently recovered and the fraction of thehydrogen evolution reaction which is kinetically faster than the nickel ion reduction decreased,which contributed to a coarse grain sized electrodeposit. The experimental results of the hardnessand the stress-strain curves were supplemented by the results of the potentiodynamic curve
    Type of Medium: Electronic Resource
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  • 6
    Electronic Resource
    Electronic Resource
    s.l. ; Stafa-Zurich, Switzerland
    Solid state phenomena Vol. 119 (Jan. 2007), p. 111-114 
    ISSN: 1662-9779
    Source: Scientific.Net: Materials Science & Technology / Trans Tech Publications Archiv 1984-2008
    Topics: Physics
    Notes: The precipitates in the base metal and the fusion zone of an Alloy 600/182 weld werecharacterized through a transmission electron microscopy. Precipitates in the Alloy 600 base metalwere identified as Cr7C3. On the other hand, (Nb,Ti)C, Al-rich and Ti-rich oxides were found on thedendritic interfaces, and tiny Cr-rich M23C6 were distributed on the grain boundaries in the Alloy182 fusion zone
    Type of Medium: Electronic Resource
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  • 7
    Electronic Resource
    Electronic Resource
    s.l. ; Stafa-Zurich, Switzerland
    Key engineering materials Vol. 345-346 (Aug. 2007), p. 1345-1348 
    ISSN: 1013-9826
    Source: Scientific.Net: Materials Science & Technology / Trans Tech Publications Archiv 1984-2008
    Topics: Mechanical Engineering, Materials Science, Production Engineering, Mining and Metallurgy, Traffic Engineering, Precision Mechanics
    Notes: A primary water stress corrosion cracking (SCC) and an outside diameter SCC haveoccurred in the steam generator (SG) tubes of nuclear power plants around the world. It is importantto establish the repair criteria for the degraded tubes to assure a reactor integrity, and yet maintainthe plugging ratio within the limits needed for an efficient operation. For assessment andmanagement of the degradation, it became crucial to understand initial leak behaviors under a smallpressure and leak rate evolution under a constant pressure of SCC flaws. Stress corrosion crackedtube specimens were prepared by using a room temperature cracking technique, and leak behaviorsof these tubes were measured at room temperature. Water pressure inside the tube was increasedslowly in a step like manner with a designated holding time. Water leak rates just after a ligamentrupture were measured by collecting the leaked water in a plastic container for a designated time. Aleak rate was calculated by dividing the amount of water by the time. Under 3.45 MPa, a smallwater droplet was formed, but it did not grow after a 10 minute holding period at a constantpressure of 3.45 MPa. A throughwall crack seemed to open at around 8.28 MPa (1200 psi). Sometubes with 100 % through wall cracks did not show a leakage at 10.8 MPa, which is a typicalpressure difference of pressurized water reactors (PWRs) during a normal operation. The higher thepressure was applied, the larger the rates of increase with the time were. Axial cracks showed alower leak pressure than that of the circumferential cracks, which might be from a higher hoopstress than the axial stress. A large open and long axial crack showed an increasing leak rate withthe time at a constant pressure
    Type of Medium: Electronic Resource
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