journal article·2017-12

Quasi in-situ energy dispersive X-ray spectroscopy observation of matrix and solute interactions on Y Ti O oxide particles in an austenitic stainless steel under 1 MeV Kr2+ high temperature irradiation

Adam J. Brooks, Zhongwen Yao, Mark R. Daymond, Hongbing Yu, Mark A. Kirk, Zhangjian Zhou, Guangming Zhang

Acta Materialia· Volume 141
Publisher page

Abstract

Abstract This article presents a novel quasi in-situ analysis, which allowed for examining the same microstructural area before and after irradiation, in two distinct facilities. One facility is used for the irradiation, and one for the energy dispersive X-ray spectroscopy (EDX) in a transmission electron microscope (TEM). The material studied is an austenitic oxide dispersion strengthened (ODS) stainless steel, modeled after commercial grade 310 L (25Cr 20Ni 2Mo-0.02C-0.4N-0.35Y2O3-0.5Ti-bal.Fe), which is synthesized from a powder metallurgy fabrication route using hot isostatic pressing. ODS materials are suitable for applications in: structural, highly corrosive, nuclear, and electromagnetic field environments. In fact, new generation fusion systems represent all four of these demands at the same time. The 310-ODS material is irradiated to ∼1.5dpa at 520OC with 1 MeV Kr2+ 7.5 × 1014 ions cm−2 (∼1.25 × 10−3 dpa/s). Quasi in-situ EDX line scans are presented, focusing on the interactions of: Fe, Cr, Ni, Y, Ti, and O. The examined particles are two Ti-rich structures, which present themselves as non-stoichiometric oxides (>200 nm) embedded within the iron matrix. The Y/Ti at% ratios in both observed particles decreased slightly from 0.34 ± 0.07 and 0.28 ± 0.04, to 0.26 ± 0.08 and 0.20 ± 0.06 respectively, suggesting a dissolution mechanism has initiated under this irradiation condition. It is often a question of dissolution vs. amorphization in these materials. Included is a detailed discussion of these two mechanisms as a function of temperature, fluence, and irradiating energy, with contrast to the current literature. Furthermore, attached is a data-in-brief (DiB), which includes the EDX spectrum and raw data captured from the experiment.
Source: openaire · Quality: candidate unverified · Source record ↗

Research context

OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Nuclear materials and radiation effects

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

References (52)

Show source-provided references
1. Effects of plastic deformations on microstructure and mechanical properties of ODS-310 austenitic steel10.1016/j.jnucmat.2012.07.014 ↗
2. Microstructure and mechanical properties of 16 Cr-ODS ferritic steel for advanced nuclear energy system10.1088/1742-6596/419/1/012036 ↗
3. Processing and characterization of a hipped oxide dispersion strengthened austenitic steel10.1016/j.jnucmat.2011.08.027 ↗
4. Recent developments in irradiation-resistant steels10.1146/annurev.matsci.38.060407.130315 ↗
5. Fabrication and characterization of ODS austenitic steels10.1016/j.jnucmat.2010.12.155 ↗
6. Tensile and creep properties of an oxide dispersion-strengthened ferritic steel10.1016/S0022-3115(02)01046-2 ↗
7. Microstructural evolution of Y2O3 and MgAl2O4 ODS EUROFER steels during their elaboration by mechanical milling and hot isostatic pressing10.1016/j.jnucmat.2004.06.010 ↗
8. On ball-milled ODS ferritic steel recrystallization: from as-milled powder particles to consolidated state10.1007/s10853-014-8783-1 ↗
9. The formation and evolution of oxide particles in oxide-dispersion-strengthened ferritic steels during processing10.1016/j.actamat.2012.12.042 ↗
10. Effects of milling process and alloying additions on oxide particle dispersion in austenitic stainless steel10.1016/j.jnucmat.2014.01.025 ↗
11. Structural evolution of oxide dispersion strengthened austenitic powders during mechanical alloying and subsequent consolidation10.1016/j.powtec.2014.12.008 ↗
12. Structural materials for Gen-IV nuclear reactors: challenges and opportunities10.1016/j.jnucmat.2008.08.044 ↗
13. Overview of EU DEMO design and R&D activities10.1016/j.fusengdes.2014.01.070 ↗
14. Materials challenges for ITER – current status and future activities10.1016/j.jnucmat.2007.03.017 ↗
15. Developing structural, high-heat flux and plasma facing materials for a near-term DEMO fusion power plant: the EU assessment10.1016/j.jnucmat.2014.06.014 ↗
16. Perspective of ODS alloys application in nuclear environments10.1016/S0022-3115(02)01043-7 ↗
17. Status of the ITER vacuum vessel construction10.1016/j.fusengdes.2013.12.056 ↗
18. ITER plasma-facing components10.1016/j.fusengdes.2010.09.013 ↗
19. Overview of recent European materials R&D activities related to ITER10.1016/j.jnucmat.2004.04.008 ↗
20. Assessment and selection of materials for ITER in-vessel components10.1016/S0022-3115(00)00305-6 ↗
21. Nuclear properties of magnet structural materials for fusion reactors10.1016/0022-3115(91)90289-J ↗
22. Cryogenic properties of new austenitic stainless steel for fusion reactor superconducting magnets10.1016/0022-3115(89)90543-6 ↗
23. Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys10.1557/jmr.2015.32 ↗
24. Nano ZrO2 particles in nanocrystalline Fe–14Cr–1.5Zr alloy powders10.1016/j.jnucmat.2014.05.067 ↗
25. Response of nanostructured ferritic alloys to high-dose heavy ion irradiation10.1016/j.jnucmat.2013.11.002 ↗
26. A review of advantages of high-efficiency X-ray spectrum imaging for analysis of nanostructured ferritic alloys10.1016/j.jnucmat.2014.11.134 ↗
27. Size effect of primary Y2O3 additions on the characteristics of the nanostructured ferritic ODS alloys: comparing as-milled and as-milled/annealed alloys using S/TEM10.1016/j.jnucmat.2014.05.014 ↗
28. Spectral and raw quasi in-situ energy dispersive X-ray data captured via a TEM analysis of an ODS austenitic stainless steel sample under 1MeV Kr2+ high temperature irradiation10.1016/j.dib.2017.08.030 ↗
29. Nanoparticles from mechanical attrition
30. Mechanical alloying and milling10.1016/S0079-6425(99)00010-9 ↗
31. When do oxide precipitates form during consolidation of oxide dispersion strengthened steels?10.1016/j.jnucmat.2016.10.017 ↗
32. Comments on DPA calculation methods for ion beam driven simulation irradiations
33. Stoller · 2012
34. Quantitative EDXS: influence of geometry on a four detector system10.1016/j.ultramic.2016.10.005 ↗
35. Heinrich · 1991 · 9
36. An accurate computer correction program for quantitative electron probe microanalysis10.1007/BF01244563 ↗
37. Alvisi · 2006 · 406
38. Core/shell structures of oxygen-rich nanofeatures in oxide-dispersion strengthened Fe-Cr alloys10.1063/1.3000965 ↗
39. Effects of heavy-ion irradiation on the grain boundary chemistry of an oxide-dispersion strengthened Fe–12wt.% Cr alloy10.1016/j.jnucmat.2010.12.251 ↗
40. Nanoscale characterisation of ODS–Eurofer 97 steel: an atom-probe tomography study10.1016/j.jnucmat.2010.02.007 ↗
41. Effect of Ti and Cr on dispersion, structure and composition of oxide nano-particles in model ODS alloys10.1016/j.actamat.2015.06.032 ↗
42. Radiation stability of nanoclusters in nano-structured oxide dispersion strengthened (ODS) steels10.1016/j.jnucmat.2012.11.021 ↗
43. Radiation induced microstructures in ODS 316 austenitic steel under dual-beam ions10.1016/j.jnucmat.2014.06.024 ↗
44. Ion irradiation-induced precipitation of Cr23C6 at dislocation loops in austenitic steel10.1016/j.scriptamat.2012.10.002 ↗
45. In situ TEM study of the stability of nano-oxides in ODS steels under ion-irradiation10.1016/j.jnucmat.2011.12.009 ↗
46. Controlling diffusion for a self-healing radiation tolerant nanostructured ferritic alloy10.1016/j.jnucmat.2014.12.048 ↗
47. Amorphization of oxides in ODS materials under low and high energy ion irradiations10.1016/j.jnucmat.2011.01.065 ↗
48. Amorphization of oxides in ODS steels/materials by electronic stopping power10.1016/j.jnucmat.2012.01.026 ↗
49. Radiation stability of the ODS alloys against swift heavy ion impact10.1016/j.jnucmat.2013.07.017 ↗
50. Heavy-ion irradiation effects on structures and acid dissolution of pyrochlores10.1016/S0022-3115(00)00708-X ↗
51. Stability of nano-oxides upon heavy ion irradiation of an ODS material10.1016/j.jnucmat.2010.12.068 ↗
52. Ion irradiation of rare-earth- and yttrium-titanate-pyrochlores10.1016/S0168-583X(00)00030-6 ↗