journal article·2026-04

Insight into the corrosion fatigue crack growth mechanism of a Zr Sn Nb alloy in simulated PWR primary water

Yuqi Zheng, Jun Xiao, Ting Xiao, Wanli Ma, Jingjing Liao, Yong Chen, Hao Wang, Qi Xu

Corrosion Science· Volume 262
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: Nuclear Materials and Properties · Nuclear Engineering Thermal-Hydraulics · Thermodynamic and Structural Properties of Metals and Alloys

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

References (41)

Show source-provided references
1. Materials challenges in nuclear energy10.1016/j.actamat.2012.11.004 ↗
2. Influence of dissolved hydrogen on the early stage corrosion behavior of zirconium alloys in simulated light water reactor coolant conditions10.1016/j.corsci.2017.11.026 ↗
3. R. Adamson, F. Garzarolli, B. Cox, Corrosion mechanisms in zirconium alloys, ZIRAT12 Special Topic Report, 2007.
4. Zirconium alloys for LWR fuel cladding and core internals
5. Low-cycle fatigue behaviors of 316LN austenitic stainless steel in borated and lithiated high temperature water with different levels of dissolved oxygen10.1016/j.corsci.2020.109048 ↗
6. Fatigue crack propagation rates for notched 304 stainless steel specimens in elevated temperature water10.1115/1.1767859 ↗
7. Life prediction by mechanistic modeling and system monitoring of environmental cracking of iron and nickel alloys in aqueous systems10.1016/0025-5416(88)90564-2 ↗
8. Effects of oxide on fatigue crack growth behaviour of type 347 stainless steel in PWR water conditions10.1111/ffe.12290 ↗
9. Fatigue life and crack growth mechanisms of the Type 316LN austenitic stainless steel in 310℃ deoxygenated water10.1080/18811248.2007.9711340 ↗
10. Low cycle fatigue behaviors of type 316LN austenitic stainless steel in 310 °C deaerated water-fatigue life and dislocation structure development10.1016/j.msea.2007.07.023 ↗
11. Effect of heat treatment on fatigue crack growth behavior of 316NG austenitic stainless steel in deaerated water at 325C10.1016/j.jnucmat.2021.153298 ↗
12. Fatigue crack growth of Z2CND18–12 N austenitic stainless steel and its heat-affected zone in a dissimilar metal weld joint in 325°C water10.5006/4114 ↗
13. Effect of dissolved oxygen and temperature on fatigue crack growth rate behaviour of SA312 Type 304L(N) material in water environment10.1016/j.ijfatigue.2016.10.022 ↗
14. Effects of 100 ppb dissolved oxygen on low-cycle fatigue behaviors of 316LN austenitic stainless steel in borated and lithiated high temperature water and mechanism behind these effects10.1016/j.corsci.2020.108567 ↗
15. Effects of dissolved hydrogen on low-cycle fatigue behaviors and hydrogen uptake of 316LN austenitic stainless steel in simulated pressurized water reactor primary water10.1016/j.ijfatigue.2019.105457 ↗
16. Environmentally aggravated fatigue cracking of Zircaloy-2
17. Fatigue properties of Zircaloy-2 in a PWR environment
18. Factors affecting fatigue crack growth rates in Zircaloy components in reactor water environments
19. Fatigue behavior of irradiated and unirradiated zircaloy and zirconium
20. The increase in fatigue crack growth rates observed for Zircaloy-4 in a PWR environment10.1016/j.jnucmat.2017.11.015 ↗
21. O.E. Lepik, D.M. McCluskey, Fatigue crack growth behaviour of Zr-2.5 Nb in a CANDU reactor water environment, 1993.
22. Pre-transition corrosion behavior of SZA-4 and ZIRLO alloys in dissolved oxygen aqueous condition at 360℃10.3901/JME.2019.08.088 ↗
23. Corrosion of new zirconium claddings in 500 ℃/10.3 MPa steam: effects of alloying and metallography10.1007/s40195-018-0857-7 ↗
24. Study on corrosion resistance of N36 zirconium alloy in LiOH aqueous solution10.4236/wjnst.2018.82004 ↗
25. High-pressure corrosion fatigue experiments employing diverse methodologies for assessing rates of crack propagation10.1016/j.jmrt.2024.07.058 ↗
26. Corrosion fatigue behavior and crack-tip characteristic of 316LN stainless steel in high-temperature pressurized water10.1016/j.jnucmat.2019.02.040 ↗
27. Characterization of the roles of electrochemistry, convection and crack chemistry in stress corrosion cracking
28. Effects of chloride and oxygen on stress corrosion cracking of cold worked 316/316L austenitic stainless steel in high temperature water10.1016/j.corsci.2016.04.035 ↗
29. Modelling of crack chemistry in sensitized stainless steel in boiling water reactor environments10.1016/S0010-938X(97)89342-0 ↗
30. Stress corrosion cracking of uni-directionally cold worked 316NG stainless steel in simulated PWR primary water with various dissolved hydrogen concentrations10.1016/j.corsci.2011.04.013 ↗
31. Redox potential measurements in high temperature aqueous systems10.1149/1.2127400 ↗
32. The impact of radiolytic yield on the calculated ECP in PWR primary coolant circuits10.1016/j.jnucmat.2006.10.012 ↗
33. Corrosion of zirconium alloys used for nuclear fuel cladding10.1146/annurev-matsci-070214-020951 ↗
34. Effect of hydrogen content on low-cycle fatigue behavior of Zr-Sn-Nb alloy10.1016/S1875-5372(13)60006-5 ↗
35. Hydride-phase formation and its influence on fatigue crack propagation behavior in a zircaloy-4 alloy10.1007/s11661-010-0342-z ↗
36. Metallographic studies of fatigue in 20% cold-worked zircaloy-2 containing zirconium hydride10.1016/0022-3115(72)90141-9 ↗
37. In-situ investigation of the fatigue crack initiation and propagation behavior of Zircaloy-4 with different hydrogen contents at RT and 300° C10.1016/j.jnucmat.2020.152065 ↗
38. Life prediction by mechanistic modelling and system monitoring of environmental cracking of Fe and Ni alloys in aqueous systems10.1016/0025-5416(88)90564-2 ↗
39. Perspective and direction of stress corrosion cracking in hot water
40. Hudak · 1988
41. Baboian · 2005 · 20