Residual stress assessment of nickel-based alloy 690 welding parts

Lee, Sang-Hwan; Chang, Yoon‐Suk; Kim, Sung Woo

doi:10.1016/j.engfailanal.2015.03.022

Cited by 11 publications

(8 citation statements)

References 26 publications

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“…Before the crack growth analyses of the CT specimen for ER316L, WRS simulation of a welding block was preceded. The temperature‐dependent thermal and mechanical properties of the TP316 base metal and ER316L weld metal used in this study were retrieved from previous studies and materials specification sheets of the manufacturers. In order to simulate material hardening behaviour, from the conservative engineering viewpoint, isotropic hardening model with incremental plasticity option was adopted instead of others such as kinematic and combined ones .…”

Section: Verification Of the Proposed Methodsmentioning

confidence: 99%

Crack growth evaluation by XFEM for nuclear pipes considering thermal aging embrittlement effect

Sim

Chang

2018

Fatigue Fract Eng Mat Struct

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Since thermal aging embrittlement (TE) causes loss of fracture toughness and may lead to failure, it is one of structural integrity issues to be assessed in nuclear industry. In this study, crack growth simulation by using extended finite element method (XFEM) was carried out for CF8M base metal and ER316L weld metal, which are typical vulnerable materials. First, user subroutines were constructed to incorporate variation of mechanical properties of two materials due to the TE. In particular, with regard to ER316L, weld residual stress (WRS) distribution was considered. Second, validity of the subroutines and XFEM was confirmed by comparing with analytical and experimental data. Finally, crack growth analyses for nuclear pipes were performed by applying the verified methodology. Thereby, differences of the crack growth amounts and paths as the presence or absence of the TE and WRS were quantified and discussed.

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Section: Verification Of the Proposed Methodsmentioning

confidence: 99%

Crack growth evaluation by XFEM for nuclear pipes considering thermal aging embrittlement effect

Sim

Chang

2018

Fatigue Fract Eng Mat Struct

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“…With the concept of total input heat flow equivalence, the heat flow denoted by Q flux [J] generated to build a single bead with volume V flux [m 3 ] by applying unit heat flux density, q flux , during the duration of welding time, Δ t flux , can be represented as

Q_{flux} = q_{flux} \times V_{flux} \times Δ t_{flux}

where q flux is defined as the unit heat flux density (= ηVI / Av Δ t ) flux . η flux is the welding efficiency with a range of 0.7–0.8 . V flux [V], I flux [A] and A flux [m 2 ] are the welding voltage, welding current and cross‐sectional area of a weld wire, respectively.…”

Section: Finite Element Modellingmentioning

confidence: 99%

“…Therefore, in this study, we utilized the prescribed temperature method as a valid engineering solution instead of the complex and time‐consuming heat flux method. The applicability of the prescribed temperature method is known to be simple compared with the heat flux method and to give reasonable accuracy on a solution …”

Section: Finite Element Modellingmentioning

confidence: 99%

“…The applicability of the prescribed temperature method is known to be simple compared with the heat flux method and to give reasonable accuracy on a solution. 24 Table 4 represents the welding simulation input condition. The total heat flow input used to build one welding bead is calculated by Eq.…”

Section: Heat Transfer Analysismentioning

confidence: 99%

“…25 Austenite to martensite transformation is usually regarded as non-diffusion phase change. A Koistinen-Marburger relationship 23,24 was implemented to describe the volume fraction of martensite as follows:…”

Section: Heat Transfer Analysismentioning

confidence: 99%

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Investigation of residual stresses in a repair‐welded rail head considering solid‐state phase transformation

Jun

Jeon

et al. 2016

Fatigue Fract Eng Mat Struct

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Repair welding for recovery from local damage of a rail head surface is known to cause high residual stress and can accelerate fatigue in the rail. This study examines repair‐welded rails by applying experimental and numerical approaches. In the former approach, two newly manufactured rail specimens and four repair‐welded rail specimens with two different weld depths were prepared, and their residual stresses were measured with a sectioning method. In the latter approach, a finite element repair welding simulation model was developed that adopted a prescribed temperature method with a moving block as an input heat source, and the thermal strain caused by the volume change due to solid‐state phase transformation was considered. Overall, the residual stresses correlated well between the experimental and numerical approaches. The measured high compressive residual stress of −290 MPa seems to be beneficial to prevent a crack initiation in the rail surface.

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Ductility dip cracking mechanisms and characterization: a review

Caruso,

Frame

2024

J Mater Sci

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Residual stress assessment of nickel-based alloy 690 welding parts

Cited by 11 publications

References 26 publications

Crack growth evaluation by XFEM for nuclear pipes considering thermal aging embrittlement effect

Crack growth evaluation by XFEM for nuclear pipes considering thermal aging embrittlement effect

Investigation of residual stresses in a repair‐welded rail head considering solid‐state phase transformation

Ductility dip cracking mechanisms and characterization: a review

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