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Research Papers: Materials and Fabrication

Constraint-Dependent J-R Curves of a Dissimilar Metal Welded Joint for Connecting Pipe-Nozzle of Nuclear Pressure Vessel

[+] Author and Article Information
J. Wang, F. Z. Xuan, S. T. Tu

Key Laboratory of Pressure Systems and Safety,
Ministry of Education,
East China University of Science and Technology,
Shanghai 200237, China

G. Z. Wang

Key Laboratory of Pressure Systems and Safety,
Ministry of Education,
East China University of Science and Technology,
Shanghai 200237, China
e-mail: gzwang@ecust.edu.cn

1Corresponding author.

Contributed by the Pressure Vessel and Piping Division of ASME for publication in the JOURNAL OF PRESSURE VESSEL TECHNOLOGY. Manuscript received October 19, 2013; final manuscript received October 30, 2014; published online November 21, 2014. Assoc. Editor: Wolf Reinhardt.

J. Pressure Vessel Technol 137(2), 021405 (Apr 01, 2015) (8 pages) Paper No: PVT-13-1182; doi: 10.1115/1.4028993 History: Received October 19, 2013; Revised October 30, 2014; Online November 21, 2014

In this paper, the J-R curves of two cracks (A508 HAZ crack 2 and A508/Alloy52Mb interface crack 3) located at the weakest region in an Alloy52M dissimilar metal welded joint (DMWJ) for connecting pipe-nozzle of nuclear pressure vessel have been measured by using single edge-notched bend (SENB) specimens with different crack depths a/W (different constraint). Based on the modified T-stress constraint parameter τ*, the equations of constraint-dependent J-R curves for the crack 2 and crack 3 were obtained. The predicted J-R curves using different constraint equations derived from the three pairs of crack growth amount all agree with the experimental J-R curves. The results show that the modified T-stress approach for obtaining constraint-dependent J-R curves of homogeneous materials can also be used for the DMWJs with highly heterogeneous mechanical properties (local strength mismatches) in nuclear power plants. The use of the constraint-dependent J-R curves may increase the accuracy of structural integrity design and assessment for the DMWJs of nuclear pressure vessels.

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Figures

Grahic Jump Location
Fig. 1

The DMWJ structure for connecting the pipe-nozzle of a reactor pressure vessel to safe-end pipe (a) and the joint geometry and materials (b) [33]

Grahic Jump Location
Fig. 2

The four materials composed of the DMWJ, initial crack positions and specimen orientation [35]

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Fig. 3

The loading configuration and geometry of SENB specimen for the crack 2 specimen

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Fig. 4

Experimental obtained J-R curves of SENB specimens for crack 2 and crack 3

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Fig. 5

Variation of modified τ* with log (J/0) for all specimens of crack 2 (a) and crack 3 (b)

Grahic Jump Location
Fig. 6

Variation of J versus τ* for crack 2 (a) and crack 3 (b)

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Fig. 7

Comparison of predicted J-R curves with experimental ones for crack 2: (a) Δa1 = 0.2 mm and Δa2 = 0.5 mm, (b) Δa1 = 0.5 mm and Δa2 = 0.7 mm, and (c) Δa1 = 0.2 mm and Δa2 = 0.7 mm

Grahic Jump Location
Fig. 8

Comparison of predicted J-R curves with experimental ones for crack 3: (a) Δa1 = 0.2 mm and Δa2 = 0.5 mm, (b) Δa1 = 0.5 mm and Δa2 = 0.7 mm, and (c) Δa1 = 0.2 mm and Δa2 = 0.7 mm

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