journal article·2022-08

Effect of external stress on hydride reorientation in zirconium

Yu-Jie Jia, Wei-Zhong Han

Acta Materialia· Volume 235
Publisher page

Abstract

The usage and long-term storage of nuclear fuel cladding motivate efforts to understand the effect of external stress on hydride precipitation. Here, by using in situ bending device in electrolytic hydrogen charging, the nucleation and precipitation behaviors of subsurface hydrides under different degrees of tensile stress were obtained. The number density of surface hydride bumps increases with the elastic tensile stress and reaches a peak before plastic yielding. This is related to the statistical result that the reorientation of hydride bumps reaches maximum at the end of elastic stage. Morphologies of hydride bumps varies from needle- or circular-shape to faceted, indicating hydride reorientation. The faceted hydrides have special crystallographic characteristics. Under tensile stress, the habit planes of faceted hydrides gradually transform from {0001} to {10 1 ¯ i} ( i = 1–7), even to the {10 1 ¯ 0} planes. Because of the local compressive stress, faceted hydrides growing along one <11 2 ¯ 0> direction are suppressed. External stress-stimulated tensile or compressive lattice stress on specific crystallographic planes impacts the choice of faceted/habit planes in hydride precipitation, which plays an important role in the long-term performance of Zr cladding tubes.
Source: expertdata · Quality: candidate unverified · Source record ↗

Research context

OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Hydrogen Storage and Materials

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

References (59)

Show source-provided references
1. Hydrides and delayed hydrogen cracking in zirconium and its alloys10.1179/imr.1983.28.1.92 ↗
2. In-reactor deformation of cold-worked Zr-2.5Nb pressure tubes10.1016/j.jnucmat.2007.02.017 ↗
3. Terminal solubility and partitioning of hydrogen in the alpha phase of zirconium, zircaloy-2 and zircaloy-410.1016/0022-3115(67)90047-5 ↗
4. Mechanisms of hydrogen induced delayed cracking in hydride forming materials10.1007/BF02644858 ↗
5. Precipitation of crack tip hydrides in zirconium alloys10.1016/j.jallcom.2006.09.034 ↗
6. Analysis of the pressure tube failure at pickering NGS “A” unit 2 nuclear systems department10.1179/cmq.1985.24.3.181 ↗
7. Hydride blister formation in Zr-2.5wt%Nb pressure tube alloy10.1016/S0022-3115(02)00708-0 ↗
8. Delayed hydrogen embrittlement in Zr-2.5wt percent Nb10.1016/0022-3115(74)90174-3 ↗
9. Extended dry storage of used nuclear fuel: technical issues: a USA perspective10.5516/NET.2011.43.5.405 ↗
10. Review of spent fuel integrity evaluation for dry storage10.5516/NET.06.2012.016 ↗
11. A study on the initial characteristics of domestic spent nuclear fuels for long term dry storage10.5516/NET.06.2012.082 ↗
12. Hydrogen in zirconium alloys: a review10.1016/j.jnucmat.2019.02.042 ↗
13. Effect of alloying elements on the properties of Zr and the Zr–H system10.1016/j.jnucmat.2013.10.040 ↗
14. Intergranular δ-hydride nucleation and orientation in zirconium alloys10.1016/j.actamat.2011.07.054 ↗
15. Resistance to hydride formation in zirconium: an emerging possibility10.1016/j.actamat.2006.06.004 ↗
16. Dislocation-mediated hydride precipitation in zirconium
17. The effect of stress on hydride precipitation10.1016/0036-9748(81)90148-4 ↗
18. Strain-dependent chemical reaction on inhomogeneous surfaces10.1021/acs.jpcc.6b07971 ↗
19. The influence of external stress/strain on the uranium-hydrogen reaction10.1016/j.jnucmat.2018.07.058 ↗
20. Hydride reorientation in zircaloy-4 cladding10.1016/j.jnucmat.2007.06.012 ↗
21. Influence of temperature and hydrogen content on stress-induced radial hydride precipitation in Zircaloy-4 cladding10.1016/j.jnucmat.2014.06.049 ↗
22. Stress reorientation of hydrides in zirconium-2.5% niobium10.1016/0022-3115(75)90132-4 ↗
23. Effect of texture, grain size, and cold work on the precipitation of oriented hydrides in zircaloy tubing and plate10.1016/0022-3115(66)90036-5 ↗
24. The influence of stress state on the reorientation of hydrides in a zirconium alloy10.1016/j.jnucmat.2016.05.013 ↗
25. Effects of applied load on formation and reorientation of zirconium hydrides: a multiphase field modeling study10.1016/j.commatsci.2021.110367 ↗
26. In situ study of hydride precipitation kinetics and re-orientation in zircaloy using synchrotron radiation10.1016/j.actamat.2010.07.018 ↗
27. Hydride platelet reorientation in zircaloy studied with synchrotron radiation diffraction10.1520/JAI103033 ↗
28. Effects of hydride morphology on the embrittlement of zircaloy-4 cladding10.1016/j.jnucmat.2014.09.025 ↗
29. Influence of hydride orientation on fracture toughness of CWSR Zr-2.5%Nb pressure tube material between RT and 300°C10.1016/j.jnucmat.2017.03.025 ↗
30. Effect of radial hydrides on the axial and hoop mechanical properties of zircaloy-4 cladding10.1016/j.jnucmat.2006.11.008 ↗
31. Radial-hydride embrittlement of high-burnup zircaloy-4 fuel cladding10.1080/18811248.2006.9711195 ↗
32. Crystallography of zirconium hydrides in recrystallized zircaloy-2 fuel cladding by electron backscatter diffraction10.1080/18811248.2004.9715540 ↗
33. Hydride reorientation in zircaloy-4 examined by in situ synchrotron X-ray diffraction10.1016/j.jnucmat.2016.05.029 ↗
34. Phase and texture analysis of a hydride blister in a Zr–2.5%Nb tube by synchrotron X-ray diffraction10.1016/j.actamat.2010.12.024 ↗
35. Effect of crystallite orientation and external stress on hydride precipitation and dissolution in Zr2.5%Nb10.1016/j.jnucmat.2013.12.025 ↗
36. On the consequences of hydrogen supersaturation effects in Zr alloys to hydrogen ingress and delayed hydride cracking10.1016/0022-3115(89)90241-9 ↗
37. Elastic and plastic accommodation effects on metal-hydride solubility10.1016/0001-6160(84)90133-0 ↗
38. Phase-field modeling of stacking structure formation and transition of δ-hydride precipitates in zirconium10.1016/j.actamat.2018.12.009 ↗
39. Mesoscale modeling of coherent zirconium hydride precipitation under an applied stress10.1016/j.jnucmat.2013.02.034 ↗
40. A quantitative phase field model for hydride precipitation in zirconium alloys: Part II. Modeling of temperature dependent hydride precipitation10.1016/j.jnucmat.2014.12.110 ↗
41. A phase-field model for hydride formation in polycrystalline metals: Application to δ-hydride in zirconium alloys10.1016/j.actamat.2019.09.047 ↗
42. Kiran Kumar · 2011
43. The influence of prior deformation on hydride precipitation in zircaloy10.1016/0956-7151(92)90310-B ↗
44. Hydrides in α-Ti: characterization and effect of applied external stresses10.1016/j.actamat.2005.06.004 ↗
45. Texture analysis with MTEX–free and open source software toolbox10.4028/www.scientific.net/SSP.160.63 ↗
46. Hierarchical 3D nanolayered duplex-phase Zr with high strength, strain hardening and ductility10.1103/PhysRevLett.122.255501 ↗
47. Precipitation characteristics and distributions of subsurface hydride in zirconium10.1016/j.actamat.2021.117146 ↗
48. The precipitation of γ-zirconium hydride in zirconium10.1016/0001-6160(78)90006-8 ↗
49. The dilatational misfit of zirconium hydrides precipitated in zirconium10.1016/0022-3115(73)90022-6 ↗
50. The effect of lattice defects on hydrogen solubility in palladium10.1016/0022-5088(76)90023-0 ↗
51. The effect of lattice defects on hydrogen solubility10.1016/0022-5088(80)90229-5 ↗
52. Hydrogen trapping by oxygen and dislocations in zirconium alloys10.1016/S0925-8388(96)02956-8 ↗
53. Tensile specimen geometry and the constitutive behavior of Zircaloy-410.1016/S0022-3115(02)01554-4 ↗
54. An electron optical study of hydride precipitation and growth at crack tips in zirconium10.1016/0001-6160(80)90076-0 ↗
55. The nature of γ-hydride in crept zirconium single crystals10.1016/0022-3115(77)90011-3 ↗
56. The precipitation of zirconium hydride in zirconium and zircaloy-210.1016/0022-3115(72)90021-9 ↗
57. Effect of hydrogen concentration and cooling rate on hydride precipitation in α-zirconium10.1016/0022-3115(75)90101-4 ↗
58. Study on the effects of matrix yield strength on hydride phase stability in Zircaloy-2 and Zr 2.5 wt% Nb10.1016/j.jnucmat.2011.10.051 ↗
59. Characteristics of hydride precipitation and reorientation in spent-fuel cladding, astm, Zirconium in the Nuclear Industry: 13th International Symposium, 1423, STP