journal article·2026-05

Quantitative Calculation Method of Crack Tip Strain Rate Based on Crack-Tip Creep

Y. H. Cui, J. L. Zhang

Strength of Materials· Volume 58· Issue 3
Publisher page

Abstract

No abstract is available for this record. The assistant can identify its topic from the title, but cannot infer the study’s results.

Source: Not provided · Quality: missing

Research context

OpenAlex topics: High Temperature Alloys and Creep · Fatigue and fracture mechanics · Hydrogen embrittlement and corrosion behaviors in metals

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

References (18)

Show source-provided references
1. U. Ehrnstén, P. L. Andresen, and Z. Q. Que, A review of stress corrosion cracking of austenitic stainless steels in PWR primary water, J Nucl Mater, 588, No. 1, 154815 (2024).10.1016/j.jnucmat.2023.154815 ↗
2. H. Xue, J. Liu, S. Zhang, et al., Characterization method and application of continuous variation of welded joint mechanical properties based on UMAT, Mater Report, 35, No. 1, 362–366 (2021).
3. Y. H. Cui and J. L. Zhang, Influence of stress corrosion cracking on crack tip creep and crack propagation rate in welded joints, Strength Mater, 56, No. 3, 610–616 (2024). https://doi.org/10.1007/s11223-024-00675-z10.1007/s11223-024-00675-z ↗
4. F. P. Ford, Three mechanisms of environmentally-assisted cracking, Int J Pres Ves Pip, 40, No. 55, 343–362 (1989).10.1016/0308-0161(89)90097-5 ↗
5. T. Shoji, Z. Lu, and H. Murakami, Formulating stress corrosion cracking growth rates by combination of crack tip mechanics and crack tip oxidation kinetics, Corros Sci, 52, No. 3, 769–779 (2010).10.1016/j.corsci.2009.10.041 ↗
6. T. Shoji, S. Suzuki, and R. G. Ballinger, Theoretical prediction of SCC growth behavior: threshold and plateau growth rate, in: 7th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Plant-Water Reactors (1995), pp. 881–892.
7. H. Xue and T. Shoji, Quantitative prediction of EAC crack growth rate of sensitized type 304 stainless steel in boiling water reactor environments based on EPFEM, J Press Vess-T ASME, 129, No. 3, 460–467 (2007).10.1115/1.2748827 ↗
8. M. M. Hall, Jr, Critique of the Ford-Andresen film rupture model for aqueous stress corrosion cracking, Corros Sci, 51, No. 5, 1103–1106 (2009).10.1016/j.corsci.2009.02.022 ↗
9. M. A. Thomas and G. S. Was, Creep and intergranular cracking of Ni-Cr-Fe-C in 360°C argon, Metall Mater Trans A, 25, No. 6, 1169–1183 (1994).10.1007/BF02652292 ↗
10. H. L. Yang, H. Xue, Z. Wang, and Y. B. Zhang, Effect of creep rate at crack tip on stress corrosion crack propagation rate for nickel-based alloy 600, Forging and Stamping Technology, 50, No. 1, 231–238 (2025).
11. J. L. Zhang, Y. H. Cui, H. Xue, et al., Research on SCC crack growth behavior of nickel-based alloy 600 in safe-end welded joints, Rare Metal Mat Eng, 49, No. 5, 1496–1502 (2020).
12. K. S. Li, R. Z. Wang, X. C. Zhang, et al., Creep-fatigue life prediction based on multi-scale modeling approach, Press Vess Technol, 38, No. 11, 73–81 (2021).
13. Y. H. Cui, J. L. Zhang, and X. L. Li, Influence of yield stress on the SCC creep mechanical field and growth rate at the tip of 304 stainless steel, Foundry Technology, 41, No. 12, 1117–1121 (2020).
14. J. L. Zhang, H. Xue, Y. H. Cui, et al., Influence of different crack propagation stages on SCC crack-tip creep field, J Xi’an University of Science and Technology, 41, No. 1, 145–151 (2021).
15. ASTM E399-90. Standard Test Method for Plane-Strain Fracture Toughness of Metallic Materials, ASTM International (2002).
16. N. N. Han and J. F. Gu, Creep behavior of Inconel 600 alloy used for nuclear power, Heat Treatment of Metals, 41, No. 6, 1–3 (2016).
17. J. W. Sun, X. T. Gong, S. Wang, and X. H. Shen, Numerical simulation study on the influence of stressinduced hydrogen diffusion at the crack tip of 30CrMo steel, Process Equipment and Piping, 61, No. 4, 1–7 (2024).
18. K. Chen, J. M. Wang, D. H. Du, et al., dK/da effects on the SCC growth rates of nickel base alloys in hightemperature water, J Nucl Mater, 503, No. 1, 13–21 (2018).10.1016/j.jnucmat.2018.02.032 ↗