Study on the microstructure evolution and fracture mechanism of C7(Zr–1Nb-0.01Cu) cladding alloy with different hydrogen contents
Source abstract
Abstract
The microstructural evolution, texture characteristics, and mechanical responses of the C7 (Zr-1Nb-0.01Cu) cladding alloy were systematically investigated as a function of hydrogen content (in weight parts per million, wppm). Specimens with hydrogen concentrations of 200, 400, 600, and 800 wppm were prepared through gas-state hydrogen absorption experiment charging. The distribution of hydride phases, the interfacial characteristics between hydrides and the matrix, and the corresponding changes in mechanical properties were examined using metallographic analysis, scanning electron microscopy (SEM), electron backscatter diffraction (EBSD), and ring tensile testing. Pronounced microstructural alterations were observed with increasing hydrogen content, particularly in the precipitation behavior and spatial distribution of hydrides. Hydrides tested at 400 wppm, were predominantly distributed along grain boundaries and exhibited relatively low brittleness. Extensive hydride aggregation and the formation of a continuous network resulted in a significant increase in brittleness at 800 wppm. Ring tensile tests indicated that while the yield and tensile strengths remained largely unchanged, a marked reduction in ductility occurred, especially at higher hydrogen concentrations. The fracture mode transitioned from ductile dimple rupture to brittle cleavage. This study elucidates the effect of hydrogen content on the grain structure, hydride precipitation behavior, and mechanical properties of the C7 alloy.
Source: openalex_inverted_index · Quality: baseline
Research context
OpenAlex topics: Nuclear Materials and Properties · Hydrogen Storage and Materials · Hydrogen embrittlement and corrosion behaviors in metals
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (33)
Show source-provided references
1. Hydrogen in zirconium alloys: a review10.1016/j.jnucmat.2019.02.042 ↗
2. The interface structure and bonding properties of TiC / CoCrFeNi based on first-principles calculations10.1016/j.jallcom.2026.186185 ↗
3. Hydrogen pickup measurements in zirconium alloys: relation to oxidation kinetics10.1016/j.jnucmat.2014.03.001 ↗
4. Thermodynamics and kinetics of delayed hydride cracking in zirconium alloys: a review10.1016/j.jnucmat.2024.155006 ↗
5. Zirconium hydride precipitation kinetics in Zr-4 observed with synchrotron X-ray diffraction10.1016/j.jnucmat.2015.04.025 ↗
6. Investigating zirconium alloy corrosion with advanced experimental techniques: a review10.1016/j.jnucmat.2023.154586 ↗
7. In situ TiBX/TiXNiY/TiC reinforced Ni60 composites by laser cladding and its effect on the tribological properties10.1016/j.ceramint.2022.10.087 ↗
8. Hydride-induced responses in the mechanical behavior of Zr-4 sheets10.3390/met14020177 ↗
9. Multi-physics modeling of delayed hydride cracking in zirconium alloys10.1016/j.jmps.2019.07.020 ↗
10. Effects and quantitative analyses of mechanical properties on strain limit during plastic deformation of zirconium alloys10.1007/s12289-023-01746-3 ↗
11. Pressurized water reactor fuel crud and corrosion modeling10.1007/s11837-011-0141-z ↗
12. Improved and innovative accident-tolerant nuclear fuel materials considered for retrofitting light water reactors—A review10.3390/cmd4030024 ↗
13. Improvement and prediction technology of the water-side corrosion of zirconium alloy: the developmental tendency10.1088/1742-6596/2821/1/012016 ↗
14. Effect of hydride orientation on tensile properties and crack formation in zirconium alloy cladding tubes10.1016/j.jnucmat.2024.155120 ↗
15. Thermal-mechanical coupling simulation and experimental study of ultrasound-assisted laser cladding of Ni60 coating10.1016/j.jallcom.2025.180270 ↗
16. Influence of temperature and hydrogen content on the transverse mechanical properties of Zr-4 fuel cladding10.1016/j.pnucene.2022.104439 ↗
17. Expansion deformation behavior of zirconium alloy claddings with different hydrogen concentrations10.1016/j.jnucmat.2021.153082 ↗
18. Mechanical property evaluation of high burn-up nuclear fuel cladding using the ring tensile test10.1007/s12540-009-0547-0 ↗
19. Exploring the hydride-slip interaction in zirconium alloys10.1016/j.actamat.2023.119388 ↗
20. The role of hydrides and precipitates on the strain localisation behaviour in a zirconium alloy10.1016/j.actamat.2023.119327 ↗
21. Mechanisms of hydride nucleation, growth, reorientation, and embrittlement in zirconium: a review10.3390/ma16062419 ↗
22. Effects of hydrogen contents on the mechanical properties of Zr-4 sheets10.1016/j.msea.2016.02.051 ↗
23. Corrosion of zirconium fuel cladding inside a boiling water reactor: a post-irradiation study by atom probe tomography10.1016/j.actamat.2025.121020 ↗
24. Reorientation of hydrides and its effect on the mechanical properties of zr-nb-sn-fe cladding tubes10.1080/18811248.2005.9726382 ↗
25. Oxidation of typical Zr-1 Nb alloy in high-temperature air under 700–900°C10.1016/j.corsci.2022.110701 ↗
26. Oxidation behavior of Zr–1Nb corroded in air at 400°C after plasma immersion titanium implantation10.3390/met8010027 ↗
27. Hydride growth mechanism in Zr-4: investigation of the partitioning of alloying elements10.1017/S1431927619013266 ↗
28. Hydrogen diffusion in Zr-2.5Nb pressure tubes specimens between 300°C-400°C by in-situ neutron imaging experiments10.1088/1742-6596/2605/1/012037 ↗
29. Corrosion properties of Zr-4 and M5 under simulated PWR water conditions10.13182/NT16-54 ↗
30. Hydrogen absorption behavior of Zr-Nb alloy and phase transformations
31. Microstructural analysis of interconnected δ-hydride structures in a zirconium alloy10.1016/j.actamat.2025.121473 ↗
32. Estimating dislocation density from electron backscatter diffraction data for an AZ31/Mg-0.6Gd hybrid alloy fabricated by high-pressure torsion10.1080/14786435.2024.2308203 ↗
33. Dual strengthened control of recrystallization behavior on CVCDE magnesium alloy containing characteristic structure10.1007/s40195-023-01594-9 ↗