Effect of Nb and Fe on damage evolution in a Zr-alloy during proton and neutron irradiation
Source abstract
Abstract
Detailed analysis was carried out on proton and a neutron irradiated Nb-containing Zr-alloy to study the evolution of dislocation loop size and densities as well as the formation and evolution of irradiation-induced precipitation/clustering. The results obtained here have been contrasted against previously published work on a Nb-free Zr-alloy [1, 2] to investigate the mechanistic reason for the improved resistance to irradiation-induced growth of Nb-containing Zr alloys. The combined use of bright field scanning transmission electron microscopy, ultra-high-resolution energy dispersive spectroscopy and atom probe tomography analysis provides evidence of evenly distributed radiation-induced Nb clusters that have formed during the early stage of proton irradiation and Fe-rich nano-rods near Fe-containing second phase particles. The former seems to have a profound effect on loop and subsequent loop formation, keeping loop size small but number density high while loops seem to initially form at similar dose levels compared to a Nb-free alloy but loop line density does not increase during further irradiation. It is hypothesized that the formation of the Nb nano-precipitates/clusters significantly hinders mobility and growth of loops, resulting in a small size, high number density and limited ability of loops to arrange along basal traces compared to Nb-free Zr-alloys. It is suggested that it is the limited loop arrangement that slows down loop formation and the root cause for the high resistance of Nb-containing Zr-alloys to irradiation-induced growth.
Source: expertdata · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Nuclear reactor physics and engineering
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (60)
Show source-provided references
1. Nano-scale chemical evolution in a proton-and neutron-irradiated Zr alloy10.1016/j.jnucmat.2017.01.049 ↗
2. The effect of matrix chemistry on dislocation evolution in an irradiated Zr alloy10.1016/j.actamat.2017.03.024 ↗
3. Buckley · 1962
4. 4.01 - radiation effects in zirconium alloys
5. Shape and volume changes during irradiation growth of Zircaloy-210.1016/0022-3115(80)90262-7 ↗
6. Irradiation growth of zircaloy
7. A review of microstructure evolution in zirconium alloys during irradiation10.1016/0022-3115(88)90093-1 ↗
8. 〈c〉 Component dislocations in annealed Zircaloy irradiated at about 570 K10.1016/0022-3115(86)90218-7 ↗
9. Effect of irradiation on the microstructure of zircaloy-4
10. Influence of structure-phase state of Nb containing Zr alloys on irradiation-induced growth10.1520/JAI12431 ↗
11. Accelerated irradiation growth of zirconium alloys
12. c-Component dislocations in neutron irradiated zircaloy-210.1016/0022-3115(83)90301-X ↗
13. The formation of c-component defects in zirconium alloys during neutron irradiation10.1016/0022-3115(87)90072-9 ↗
14. Irradiation-induced growth and microstructure of recrystallized, cold worked and Quenched zircaloy-2, NSF, and E635 alloys10.1520/JAI101115 ↗
15. Point defect diffusion in α-Zr10.1016/0022-3115(88)90091-8 ↗
16. The effect of iron on dislocation evolution in model and commercial zirconium alloys
17. Radiation-induced precipitation in zircaloy-210.1016/0022-3115(88)90106-7 ↗
18. Influence of neutron irradiation on dislocation structure and phase composition of Zr-base alloys
19. Microstructural stability of M5 (TM) alloy irradiated up to high neutron fluences10.1520/JAI12332 ↗
20. Radiation damage of E635 alloy under high dose irradiation in the VVER-1000 and BOR-60 reactors10.1520/JAI102941 ↗
21. Zirconium alloy E635 as a material for fuel rod cladding and other components of VVER and RBMK cores
22. Structure-phase state, corrosion and irradiation properties of Zr-Nb-Fe-Sn system Alloys
23. Effect of tin on the irradiation growth of polycrystalline zirconium10.1016/0022-3115(84)90060-6 ↗
24. ZIRLO™ - an alloy development success10.1520/JAI12942 ↗
25. In-reactor corrosion performance of ZIRLO™ and zircaloy-4
26. Development of a cladding alloy for high burnup
27. Improved ZIRLOTM cladding performance through chemistry and process modifications
28. The effect of Sn on autoclave corrosion performance and corrosion mechanisms in Zr–Sn–Nb alloys10.1016/j.actamat.2013.03.046 ↗
29. Influence of zirconium alloy chemical composition on microstructure formation and irradiation induced growth
30. Iron redistribution in a zirconium alloy after neutron and proton irradiation studied by energy-dispersive X-ray spectroscopy (EDX) using an aberration-corrected (scanning) transmission electron microscope10.1016/j.jnucmat.2014.08.034 ↗
31. Experimental study of the nucleation and growth of c-component loops under charged particle irradiations of recrystallized Zircaloy-410.1016/j.jnucmat.2011.11.061 ↗
32. Effect of proton and Ne irradiation on the microstructure of Zircaloy 4
33. In situ studies of phase transformations in zirconium alloys and compounds under irradiation
34. Precipitation in Zr-2.5Nb enhanced by proton irradiation10.1016/0022-3115(93)90089-H ↗
35. ZIRLO TM cladding improvement10.1520/JAI101188 ↗
36. The formation of c-component defects in zirconium alloys during neutron irradiation10.1016/0022-3115(87)90072-9 ↗
37. An overview of microstructural and experimental factors that affect the irradiation growth behavior of zirconium alloys
38. On the use of SRIM for computing radiation damage exposure10.1016/j.nimb.2013.05.008 ↗
39. Was · 2007
40. Gault · 2012
41. Williams · 2009
42. The determination of foil thickness by scanning transmission electron microscopy10.1002/pssa.2210310251 ↗
43. Zuo · 2013
44. EELS log-ratio technique for specimen-thickness measurement in the TEM10.1002/jemt.1060080206 ↗
45. Egerton · 2011
46. Measurement of local thickness by electron energy-loss spectroscopy10.1016/0304-3991(87)90148-3 ↗
47. Toward a better understanding of the hydrogen impact on the radiation induced growth of zirconium alloys10.1016/j.jnucmat.2013.05.045 ↗
48. The effect of iron on dislocation evolution in model and commercial Zirconium alloys
49. Microstructural evolution of M5TM7 alloy irradiated in PWRs up to high fluences—comparison with other Zr-based alloys
50. The role of Fe on the solubility of Nb in α-Zr10.1016/j.jnucmat.2008.10.004 ↗
51. Anomalous self-diffusion in a single crystal of α-zirconium10.1016/0022-3115(84)90030-8 ↗
52. Diffusion in α-Ti and Zr10.2320/matertrans.44.2 ↗
53. Defect accumulation behaviour in hcp metals and alloys10.1016/S0022-3115(99)00172-5 ↗
54. Microstructural Evolution of Q12TM alloy irradiated in PWR and comparison with other Zr base alloys
55. Irradiation-induced microstructural changes in Zr-1% Sn-1% Nb-0.4% Fe10.1016/S0022-3115(96)00453-9 ↗
56. The evolution of microstructure and deformation stability in Zr-Nb-(Sn, Fe) alloys under neutron irradiation
57. Irradiation creep and growth behavior, and microstructural evolution of advanced zr-base alloys
58. Understanding irradiation-induced nanoprecipitation in zirconium alloys using parallel TEM and APT10.1016/j.jnucmat.2018.08.033 ↗
59. Evolution of dislocation and precipitate structure in Zr alloys under long-term irradiation
60. Phase boundary of the Zr-rich region in commercial grade Zr–Nb alloys10.1016/j.jnucmat.2005.08.008 ↗