Role of refractory inclusions in the radiation-induced microstructure of APMT
Source abstract
Abstract
Abstract Kanthal APMT is a promising FeCrAl-based alloy for accident-tolerant fuel cladding because of its excellent high-temperature oxidation resistance. In this study, powder metallurgy Kanthal APMT alloy, neutron irradiated to 1.8 dpa at nominally 382 °C, was characterized. On-zone STEM imaging revealed that radiation-induced dislocation loops with Burgers vectors of a/2〈111〉 or a 〈 100 〉 and black dots tended to agglomerate in the vicinity of refractory inclusions. The densities and sizes of these loops decreased with distance from the inclusion-matrix interfaces. In addition, high-resolution energy-dispersive X-ray spectroscopy mapping was used to determine the inclusions to be either yttrium- or silicon-rich, as well as to detect the radial distribution of radiation-enhanced α′ phase near these inclusions. A high density of randomly distributed Cr-rich α′ phase was found, regardless of the presence of inclusions. Results from this study provide insights into how microstructural features can locally tailor the radiation-induced defects in FeCrAl-based alloys.
Source: openaire · 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 (57)
Show source-provided references
1. High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environments10.1016/j.jnucmat.2013.05.047 ↗
2. Advanced oxidation-resistant iron-based alloys for LWR fuel cladding10.1016/j.jnucmat.2013.06.041 ↗
3. Accident tolerant fuels for LWRs: a perspective10.1016/j.jnucmat.2013.12.005 ↗
4. Material selection for accident tolerant fuel cladding
5. Effect of steam on high temperature oxidation behaviour of alumina-forming alloys10.1179/0960340914Z.00000000058 ↗
6. Uniform corrosion of FeCrAl alloys in LWR coolant environments10.1016/j.jnucmat.2016.06.047 ↗
7. Accident tolerant FeCrAl fuel cladding: current status towards commercialization
8. Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors10.1016/j.jnucmat.2015.10.019 ↗
9. Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys10.1016/j.jnucmat.2015.06.023 ↗
10. High temperature properties of a new powder metallurgical FeCrAl alloy10.4028/www.scientific.net/MSF.461-464.455 ↗
11. Oxidation and creep limited lifetime of kanthal APMT®, a dispersion strengthened FeCrAlMo alloy designed for strength and oxidation resistance at high temperatures10.1007/s11085-012-9324-4 ↗
12. Alumina scale formation on a powder metallurgical FeCrAl alloy (kanthal APMT) at 900–1,100 °C in dry O2 and in O2 + H2O10.1007/s11085-009-9177-7 ↗
13. Tensile properties of accident-tolerant aluminum-bearing ferritic steels10.1016/j.anucene.2016.09.018 ↗
14. Precipitation of α′ in neutron irradiated commercial FeCrAl alloys10.1016/j.scriptamat.2017.08.022 ↗
15. Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys10.1016/j.jnucmat.2017.03.038 ↗
16. Thermal stability of radiation produced defects in molybdenum10.1016/0001-6160(68)90096-5 ↗
17. Neutron irradiated molybdenum-relationship of microstructure to irradiation temperature10.1080/00337577008236275 ↗
18. Evolution of fine-scale defects in stainless steels neutron-irradiated at 275 °C10.1016/S0022-3115(03)00002-3 ↗
19. Heterogeneous dislocation formation and solute redistribution near grain boundaries in austenitic stainless steel under electron irradiation10.1016/S1359-6454(01)00031-3 ↗
20. Microstructure evolution of two model ferritic/martensitic steels under in situ ion irradiation at low doses (0–2dpa)10.1016/j.jnucmat.2013.10.047 ↗
21. Heterogeneous dislocation loop formation near grain boundaries in a neutron-irradiated commercial FeCrAl alloy10.1016/j.jnucmat.2016.10.050 ↗
22. Irradiation-enhanced α′ precipitation in model FeCrAl alloys10.1016/j.scriptamat.2016.02.002 ↗
23. A combined APT and SANS investigation of α′ phase precipitation in neutron-irradiated model FeCrAl alloys10.1016/j.actamat.2017.02.077 ↗
24. Accident tolerant fuel cladding development: promise, status, and challenges10.1016/j.jnucmat.2017.12.043 ↗
25. Method for analyzing passive silicon carbide thermometry with a continuous dilatometer to determine irradiation temperature, Nuclear Instruments and Methods in Physics Research Section B
26. Dislocation loop formation in model FeCrAl alloys after neutron irradiation below 1 dpa10.1016/j.jnucmat.2017.07.061 ↗
27. Correlative microscopy of neutron-irradiated materials
28. Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys10.1557/jmr.2015.32 ↗
29. Microstructure and mechanical properties of FeCrAl alloys under heavy ion irradiations10.1016/j.jnucmat.2018.03.002 ↗
30. Hren · 2013
31. Diffraction contrast STEM of dislocations: imaging and simulations10.1016/j.ultramic.2011.07.001 ↗
32. Image processing with ImageJ
33. NIH Image to ImageJ: 25 years of image analysis10.1038/nmeth.2089 ↗
34. TEM characterization of dislocation loops in irradiated bcc Fe-based steels10.1016/j.jnucmat.2012.12.002 ↗
35. Radiation hardening in neutron-irradiated polycrystalline copper: barrier strength of defect clusters10.1016/0022-3115(91)90255-6 ↗
36. Electron radiation damage of iron in high voltage electron microscope10.1143/JPSJ.39.170 ↗
37. Observation and analysis of defect cluster production and interactions with dislocations10.1016/j.jnucmat.2004.04.298 ↗
38. Viewpoint: nanoscale chemistry and crystallography are both the obstacle and pathway to advanced radiation-tolerant materials10.1016/j.scriptamat.2017.05.014 ↗
39. Parish · 2015
40. Complementary techniques for quantification of α' phase precipitation in neutron-irradiated Fe-Cr-Al model alloys10.1017/S1431927616008199 ↗
41. Using complimentary microscopy methods to examine Ni-Mn-Si-precipitates in highly-irradiated reactor pressure vessel steels10.1016/j.actamat.2017.05.043 ↗
42. Advanced TEM characterization of oxide nanoparticles in ODS Fe–12Cr–5Al alloys10.1007/s10853-016-0111-5 ↗
43. Swelling and dislocation evolution in simple ferritic alloys irradiated to high fluence in FFTF/MOTA10.1016/0022-3115(94)00669-5 ↗
44. Microstructural examination of neutron-irradiated simple ferritic alloys, Journal of Nuclear Materials
45. Heavy-ion irradiations of Fe and Fe–Cr model alloys Part 1: damage evolution in thin-foils at lower doses10.1080/14786430802380469 ↗
46. The microstructure and tensile properties of Fe–Cr alloys after neutron irradiation at 400°C to 5.5–7.1 dpa10.1016/S0022-3115(98)00043-9 ↗
47. Behavior of ferritic/martensitic steels after n-irradiation at 200 and 300°C10.1016/j.jnucmat.2008.02.063 ↗
48. Dislocation loops and bubbles in oxide dispersion strengthened ferritic steel after helium implantation under stress10.1016/j.actamat.2007.09.016 ↗
49. Dislocation loop evolution during in-situ ion irradiation of model FeCrAl alloys10.1016/j.actamat.2017.07.011 ↗
50. Transmission electron microscopy investigation of the microstructure of Fe–Cr alloys induced by neutron and ion irradiation at 300 °C10.1016/j.jnucmat.2016.03.002 ↗
51. Defect accumulation in pure fcc metals in the transient regime: a review10.1016/0022-3115(93)90125-I ↗
52. Defect sink characteristics of specific grain boundary types in 304 stainless steels under high dose neutron environments10.1016/j.actamat.2015.01.064 ↗
53. Dependence on grain boundary structure of radiation induced segregation in a 9wt.% Cr model ferritic/martensitic steel10.1016/j.jnucmat.2012.12.026 ↗
54. Characterization of dislocation loops and chromium-rich precipitates in ferritic iron–chromium alloys as means of void swelling suppression10.1016/j.jnucmat.2007.01.069 ↗
55. Microstructural investigation of the stability under irradiation of oxide dispersion strengthened ferritic steels10.1016/j.jnucmat.2004.05.018 ↗
56. Development of damage structure in 16Cr–4Al ODS steels during electron-irradiation10.1016/j.jnucmat.2011.02.037 ↗
57. The comparison of microstructure and nanocluster evolution in proton and neutron irradiated Fe–9%Cr ODS steel to 3 dpa at 500 °C10.1016/j.jnucmat.2015.09.022 ↗