The Evaluation of Residual Stress of Girth Welded Pipe Joint

Teramae, Tetsuo; Tanaka, Yoshihiko; Matsunaga, Tomonori

doi:10.1299/kikaia.74.686

Cited by 3 publications

(1 citation statement)

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“…The maximum heat flux was defined as 0.002kJ/(mm 3 ·s) in order to obtain more than 1200°C as the maximum temperature in beads. The temperatures for every bead were also plotted, and the layer temperature was controlled lower than 180 ℃ [3]. Transformation of solid to liquid was not considered in the analysis.…”

Section: Simulation Of Weld Residual Stress With Fctdamentioning

confidence: 99%

Study of Weld Residual Stress Field in the Girth Seam H6A of Core Shroud of Boiling Water Reactor

Kaji

Igarashi

2010

18th International Conference on Nuclear Engineering: Volume 5

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Many accidents have occurred in nuclear power plants due to the intergranular stress corrosion cracking (IGSCC) in the heat affected zone (HAZ) of welded joint of the core shroud of boiling water reactors (BWRs) in past years. The IGSCC is considered to be caused by the synergistic roles of corrosion environment, neutron irradiation and the welding residual stress. After several decades, the degradation of Type 316L low carbon stainless steel used in the core shroud occurs due to the neutron irradiation and thermal cycles. The degradation can be referred to the irradiation hardening, segregation of the local chemical composition at grain boundaries and swelling. The synergistic effects of those eventually lead to the initiation and propagation of the irradiation-assisted stress corrosion cracking (IASCC) in core shroud for long operation. The HAZ of the girth seams H6a in the core shroud are sensitive to the stress corrosion cracking. We are focusing on the weld residual stress field around the girth seam H6a in the core shroud as weld. The analysis work adopted different approaches in ABAQUS to simulate the weld residual stress, and they are Static General Analysis (SGA) and Fully Coupled Temperature-Displacement Analysis (FCTDA) respectively. The former is much simple to finish the progress while cannot obtain much accurate results at the boundaries of beads due to the discontinuous temperature field in the model. The later analysis gave the much accurate results comparing with the experimental results. The axial stress field in the crossing section of the wall of the core shroud was also clarified.

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Section: Simulation Of Weld Residual Stress With Fctdamentioning

confidence: 99%

Study of Weld Residual Stress Field in the Girth Seam H6A of Core Shroud of Boiling Water Reactor

Kaji

Igarashi

2010

18th International Conference on Nuclear Engineering: Volume 5

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Effects of thermal load and cooling condition on weld residual stress in a core shroud with numerical simulation

Kaji

Igarashi

2012

Nuclear Engineering and Design

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Diffraction Angle Determination Using Cross-Correlation Algorithm for Double Exposure Method

SUZUKI,

MIURA

2024

J. Soc. Mat. Sci., Japan

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A double exposure method (DEM) was proposed as a stress measurement method using hard synchrotron X-rays for coarse-grained materials or welded parts. Up until now in the DEM, methods such as function approximation and finding straight lines from diffraction spots have been tried. However, sufficient accuracy could not be obtained for images containing a mixture of diffraction spots and rings. In this study, a new method to determine the diffraction radius is proposed. We obtain the waves of circumferential integrals for regions of interest in the front and the rear area detectors, and then determine each diffraction radius using a cross-correlation algorithm. When this method was applied to the measurement of the residual stress in the specimen of the butt-welded pipe, the diffraction radius could be determined with good accuracy. Using the cross-correlation algorithm, the diffraction radius can be determined regardless of the patterns of the diffraction spots or diffraction rings, and this method is the robust and efficient angle determination method suitable for the DEM.

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The Evaluation of Residual Stress of Girth Welded Pipe Joint

Cited by 3 publications

References 0 publications

Study of Weld Residual Stress Field in the Girth Seam H6A of Core Shroud of Boiling Water Reactor

Study of Weld Residual Stress Field in the Girth Seam H6A of Core Shroud of Boiling Water Reactor

Effects of thermal load and cooling condition on weld residual stress in a core shroud with numerical simulation

Diffraction Angle Determination Using Cross-Correlation Algorithm for Double Exposure Method

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