Simplified assessment method for defects of welding joint area at piping safety end of pressure vessel of AP1000 nuclear reactor
A technology for pressure vessels and nuclear reactors, applied in nuclear reactor monitoring, reactors, nuclear engineering, etc., can solve the problems of lack of third-generation AP1000 nuclear power equipment or component-specific defects, dissimilar metal joints cannot be accurately processed, evaluation methods, etc.
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[0060] (1) Defect characterization:
[0061] If the defect on the circumferential inner surface exceeding the standard is detected in the dissimilar metal weld area at the safe end of AP1000 or the size of the defect at the end of the evaluation period is calculated, press figure 1 Characterization determined a defect depth a = 32 mm and a defect length l = 448 mm.
[0062] (2) Determination of stress at the safe end:
[0063] The outer diameter of the pipe at the safe end of the AP1000 nuclear reactor pressure vessel is D=952.5mm, the pipe wall thickness t=82.6mm, and the designed pipe internal pressure p=17MPa, then the primary film stress can be calculated according to formula (1):
[0064] σ m = pD / 4t = 49 MPa.
[0065] As measured by the experiment, the yield strength σ of the nickel-based alloy weld zone material at the safe end at the working temperature of 340°C y =365MPa, tensile strength σ u =635MPa, then the flow stress of the material can be calculated:
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