journal article·2017-08Open access

Effect of tube processing methods on microstructure, mechanical properties and irradiation response of 14YWT nanostructured ferritic alloys

E. Aydogan, S.A. Maloy, O. Anderoglu, C. Sun, J.G. Gigax, L. Shao, F.A. Garner, I.E. Anderson, J.J. Lewandowski

Acta Materialia· Volume 134

Abstract

In this research, innovative thermal spray deposition (Process I) and conventional hot extrusion processing (Process II) methods have been used to produce thin walled tubing (∼0.5 mm wall thickness) out of 14YWT, a nanostructured ferritic alloy. The effects of processing methods on the microstructure, mechanical properties and irradiation response have been investigated by using scanning electron microscopy (SEM), transmission electron microscopy (TEM) and, micro- and nano-hardness techniques. It has been found that these two processes have a significant effect on the microstructure and mechanical properties of the as-fabricated 14YWT tubes. Even though both processing methods yield the formation of various size Y-Ti-O particles, the conventional hot extrusion method results in a microstructure with smaller, homogenously distributed nano-oxides (NOs, Y-Ti-O particles < 5 nm) with higher density. Therefore, Process II tubes exhibit twice the hardness of Process I tubes. It has also been found that these two tremendously different initial microstructures strongly affect irradiation response in these tubes under extremely high dose ion irradiations up to 1100 peak dpa at 450 °C. The finer, denser and homogenously distributed NOs in the Process II tube result in a reduction in swelling by two orders of magnitude. On the other hand, inhomogeneity of the initial microstructure in the Process I tube leads to large variations in both swelling and irradiation induced hardening. Moreover, hardening mechanisms before and after irradiation were measured and compared with detailed calculations. This study clearly indicates the crucial effect of initial microstructure on radiation response of 14YWT alloys.
Source: expertdata · Quality: candidate unverified · Source record ↗

Research context

OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · High-Temperature Coating Behaviors

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

References (59)

Show source-provided references
1. Structural materials for fission & fusion energy10.1016/S1369-7021(09)70294-9 ↗
2. Recent developments in irradiation-resistant steels10.1146/annurev.matsci.38.060407.130315 ↗
3. Irradiation-tolerant nanostructured ferritic alloys: transforming helium from a liability to an asset10.1007/s11837-010-0144-1 ↗
4. Recent progress in developing and qualifying nanostructured ferritic alloys for advanced fission and fusion applications10.1007/s11837-014-1207-5 ↗
5. Perspective of ODS alloys application in nuclear environments10.1016/S0022-3115(02)01043-7 ↗
6. Influence of particle dispersions on the high-temperature strength of ferritic alloys10.1016/j.jnucmat.2007.03.151 ↗
7. Ultrafine-grained nanocluster-strengthened alloys with unusually high creep strength10.1016/j.scriptamat.2009.06.034 ↗
8. Stability of ferritic MA/ODS alloys at high temperatures10.1016/j.intermet.2004.07.036 ↗
9. Helium effects on microstructural evolution in tempered martensitic steels: in situ helium implanter studies in HFIR10.1016/j.jnucmat.2008.12.134 ↗
10. Helium transport, fate and management in nanostructured ferritic alloys: in situ helium implanter studies10.1016/j.jnucmat.2011.01.064 ↗
11. Creep response and deformation processes in nanocluster-strengthened ferritic steels10.1016/j.actamat.2007.11.038 ↗
12. Temperature dependent dispersoid stability in ion-irradiated ferritic-martensitic dual-phase oxide-dispersion-strengthened alloy: coherent interfaces vs. incoherent interfaces10.1016/j.actamat.2016.05.042 ↗
13. Microstructural changes and void swelling of a 12Cr ODS ferritic-martensitic alloy after high-dpa self-ion irradiation10.1016/j.jnucmat.2015.09.016 ↗
14. Stability of nanosized oxides in ferrite under extremely high dose self ion irradiations10.1016/j.jnucmat.2017.01.015 ↗
15. Radiation stability of nanoclusters in nano-structured oxide dispersion strengthened (ODS) steels10.1016/j.jnucmat.2012.11.021 ↗
16. Stability of nanometer-sized oxide clusters in mechanically-alloyed steel under ion-induced displacement cascade damage conditions10.1016/j.jnucmat.2006.09.011 ↗
17. Nano-cluster stability following neutron irradiation in MA957 oxide dispersion strengthened material10.1016/j.jnucmat.2013.10.010 ↗
18. Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa10.1016/j.jnucmat.2014.06.011 ↗
19. Use of self-ion bombardment to study void swelling in advanced radiation-resistant alloys
20. Ion issues on irradiation behavior of structural materials at high doses and gas concentrations
21. Effect of bulk oxygen on 14YWT nanostructured ferritic alloys10.1016/j.jnucmat.2013.09.013 ↗
22. Effect of tube processing methods on the texture and grain boundary characteristics of 14YWT nanostructured ferritic alloys10.1016/j.msea.2016.02.085 ↗
23. Ziegler · 2013
24. EELS log-ratio technique for specimen-thickness measurement in the TEM10.1002/jemt.1060080206 ↗
25. An improved technique for determining hardness and elastic modulus using load and displacement sensing indentation experiments10.1557/JMR.1992.1564 ↗
26. The crystal structure, orientation relationships and interfaces of the nanoscale oxides in nanostructured ferritic alloys10.1016/j.actamat.2016.03.031 ↗
27. The relationship between hardness and yield stress in irradiated austenitic and ferritic steels10.1016/j.jnucmat.2004.09.024 ↗
28. Impact of the injected interstitial on the correlation of charged particle and neutron-induced radiation damage10.1016/0022-3115(83)90023-5 ↗
29. Modeling injected interstitial effects on void swelling in self-ion irradiation experiments10.1016/j.jnucmat.2015.10.002 ↗
30. Effect of defect imbalance on void swelling distributions produced in pure iron irradiated with 3.5 MeV self-ions10.1016/j.jnucmat.2014.06.002 ↗
31. Effect of self-ion irradiation on the microstructural changes of alloy EK-181 in annealed and severely deformed conditions10.1016/j.jnucmat.2017.02.006 ↗
32. Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part II—mechanistic models and predictions10.1016/j.msea.2012.08.041 ↗
33. High temperature deformation mechanisms in the 14% Cr ODS alloy10.1016/j.msea.2017.02.037 ↗
34. Microstructure refinement and strengthening mechanisms of a 9Cr oxide dispersion strengthened steel by zirconium addition10.1016/j.net.2017.01.002 ↗
35. Oxide dispersion strengthened nickel based alloys via spark plasma sintering10.1016/j.msea.2015.01.066 ↗
36. Microstructural characterization and strengthening mechanisms of a 12Cr-ODS steel10.1016/j.msea.2016.07.030 ↗
37. On the theory of radiation damage and radiation hardening
38. Observation and analysis of defect cluster production and interactions with dislocations10.1016/j.jnucmat.2004.04.298 ↗
39. On the relationship between uniaxial yield strength and resolved shear stress in polycrystalline materials10.1016/S0022-3115(00)00378-0 ↗
40. Modeling the microstructure–mechanical property relationship for a 12Cr–2W–V–Mo–Ni power plant steel10.1016/S0921-5093(03)00565-3 ↗
41. The quantitative relationship between microstructure and properties in two-phase alloys10.1179/imr.1973.18.1.31 ↗
42. Temperature dependence of the strength of fine- and ultrafine-grained materials10.1016/j.actamat.2010.10.062 ↗
43. Effect of shock loading on the microstructure, mechanical properties and grain boundary characteristics of HT-9 ferritic/martensitic steels10.1016/j.msea.2015.10.102 ↗
44. Lapointe · 1975
45. Direct observation of imperfections in crystals
46. Strengthening mechanisms (via hardness analysis) in nanocrystalline NiCr with nanoscaled Y2O3 and Al2O3 dispersoids10.1016/j.msea.2005.09.109 ↗
47. Superposition of alloy hardening, strain hardening and dynamic recovery
48. Microstructure-property relationships in tempered low alloy Cr-Mo-3.5Ni-V steel10.1179/mst.1993.9.11.1014 ↗
49. Thermodynamics and kinetics of slip
50. The effect of prestressing on the strength of neutron-irradiated copper single crystals10.1063/1.1753962 ↗
51. The influence of rolling variables on the strengthening mechanisms operating in niobium steels10.1016/0025-5416(84)90079-X ↗
52. Microstrain yield stress in neutron-irradiated copper single crystals10.1063/1.1713835 ↗
53. Precipitation hardening by large volume fractions of ordered particles
54. Modeling of structural hardening in oxide dispersion strengthened (ODS) ferritic alloys10.1007/s10853-015-9566-z ↗
55. The evolution of mechanical property change in irradiated austenitic stainless steels10.1016/0022-3115(93)90129-M ↗
56. On mechanisms controlling swelling in ferritic and martensitic alloys10.1016/0022-3115(88)90442-4 ↗
57. High resistance to helium embrittlement in reduced activation martensitic steels10.1016/S0022-3115(02)01211-4 ↗
58. Ferritic/martensitic steels for next-generation reactors10.1016/j.jnucmat.2007.05.005 ↗
59. Radiation response of alloy T91 at damage levels up to 1000 peak dpa10.1016/j.jnucmat.2016.10.003 ↗