TY - GEN
T1 - SCC properties of modified alloy 718 in BWR plant
AU - Katayama, Yoshinori
AU - Tsubota, Motoji
AU - Saito, Yoshiaki
AU - Tanaka, Norihiko
AU - Tanaka, Shigeaki
PY - 2011
Y1 - 2011
N2 - A modified alloy 718 has been developed as an alternative material to nickel-based alloy X-750 used in the boiling water reactors (BWR). Stress corrosion cracking (SCC) of a jet pump beam made of alloy X-750, occurred in a BWR plant. In order to apply modified alloy 718 to the jet pump beam, an evaluation of resistance to SCC initiation based on a uni-axial constant load (UCL) test in high temperature water was carried out. All UCL test specimens of modified alloy 718 at an applied stress beyond the yield strength in 288°C showed no failure after 10,124 hours testing. On the other hand, UCL specimens of alloy X-750 at an applied stress of 900MPa failed within 10,000 hours. Therefore, it was confirmed that modified alloy 718 had longer SCC initiation time in high temperature water than alloy X-750. Moreover, fatigue and spring properties of modified alloy 718 were also evaluated, and the characteristics of both modified alloy 718 and alloy X-750 were compared.
AB - A modified alloy 718 has been developed as an alternative material to nickel-based alloy X-750 used in the boiling water reactors (BWR). Stress corrosion cracking (SCC) of a jet pump beam made of alloy X-750, occurred in a BWR plant. In order to apply modified alloy 718 to the jet pump beam, an evaluation of resistance to SCC initiation based on a uni-axial constant load (UCL) test in high temperature water was carried out. All UCL test specimens of modified alloy 718 at an applied stress beyond the yield strength in 288°C showed no failure after 10,124 hours testing. On the other hand, UCL specimens of alloy X-750 at an applied stress of 900MPa failed within 10,000 hours. Therefore, it was confirmed that modified alloy 718 had longer SCC initiation time in high temperature water than alloy X-750. Moreover, fatigue and spring properties of modified alloy 718 were also evaluated, and the characteristics of both modified alloy 718 and alloy X-750 were compared.
KW - Alloy 718
KW - Alloy X-750
KW - Fatigue test
KW - Jet pump beam
KW - Spring properties
KW - Stress corrosion cracking
KW - Uni-axial constant load test
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M3 - Conference contribution
AN - SCOPUS:84867598304
SN - 9781622761944
T3 - 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
SP - 723
EP - 736
BT - 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
PB - John Wiley and Sons Inc.
T2 - 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
Y2 - 7 August 2011 through 11 August 2011
ER -