A combined APT and SANS investigation of α′ phase precipitation in neutron-irradiated model FeCrAl alloys
Source abstract
Abstract
Abstract FeCrAl alloys are currently under consideration for accident-tolerant fuel cladding applications in light water reactors owing to their superior high-temperature oxidation and corrosion resistance compared to the Zr-based alloys currently employed. However, their performance could be limited by precipitation of a Cr-rich α ′ phase that tends to embrittle high-Cr ferritic Fe-based alloys. In this study, four FeCrAl model alloys with 10–18 at.% Cr and 5.8–9.3 at.% Al were neutron-irradiated to nominal damage doses up to 7.0 displacements per atom at a target temperature of 320 °C. Small angle neutron scattering techniques were coupled with atom probe tomography to assess the composition and morphology of the resulting α ′ precipitates. It was demonstrated that Al additions partially destabilize the α ′ phase, generally resulting in precipitates with lower Cr contents when compared with binary Fe-Cr systems. The precipitate morphology evolution with dose exhibited a transient coarsening regime akin to previously observed behavior in aged Fe-Cr alloys. Similar behavior to predictions of the LSW/UOKV models suggests that α ′ precipitation in irradiated FeCrAl is a diffusion-limited process with coarsening mechanisms similar to those in thermally aged high-Cr ferritic alloys.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Advanced Materials Characterization Techniques
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (79)
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 cladding
3. Materials challenges in nuclear energy10.1016/j.actamat.2012.11.004 ↗
4. Designing radiation resistance in materials for fusion energy10.1146/annurev-matsci-070813-113627 ↗
5. Scoping assessments of ATF impact on late-stage accident progression including molten core-concrete interaction10.1016/j.jnucmat.2013.12.022 ↗
6. Uniform corrosion of FeCrAl alloys in LWR coolant environments10.1016/j.jnucmat.2016.06.047 ↗
7. Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors10.1016/j.jnucmat.2015.10.019 ↗
8. Microstructural stability of Fe-Cr-Al alloys at 450-550°C10.1016/j.jnucmat.2014.11.101 ↗
9. Tensile properties of neutron irradiated model and commercial FeCrAl alloys10.1016/j.jnucmat.2017.03.038 ↗
10. Deformation behavior of laser welds in high temperature oxidation resistant Fe-Cr-Al alloys for fuel cladding applications10.1016/j.jnucmat.2014.08.013 ↗
11. Void-swelling in irons and ferritic steels. I. Mechanisms of swelling suppression10.1016/0022-3115(79)90122-3 ↗
12. Void-swelling in irons and ferritic steels: II. An experimental survey of materials irradiated in a fast reactor10.1016/0022-3115(79)90123-5 ↗
13. Dislocation loops and bubbles in oxide dispersion strengthened ferritic steel after helium implantation under stress10.1016/j.actamat.2007.09.016 ↗
14. Radiation tolerance of neutron-irradiated model Fe-Cr-Al alloys10.1016/j.jnucmat.2015.06.023 ↗
15. Irradiation-enhanced α’ precipitation in model FeCrAl alloys10.1016/j.scriptamat.2016.02.002 ↗
16. Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors10.1016/j.anucene.2014.09.005 ↗
17. Screening of advanced cladding materials and UNâĂŞU3Si5 fuel10.1016/j.jnucmat.2015.03.016 ↗
18. On the swelling resistance of ferritic steel
19. On the α-α′ miscibility gap of Fe-Cr alloys10.1016/j.scriptamat.2008.08.008 ↗
20. Neutron small-angle scattering study of unmixing in Fe-Cr alloys10.1016/0956-7151(92)90094-U ↗
21. α′ precipitation in neutron-irradiated Fe-Cr alloys10.1016/j.scriptamat.2013.10.001 ↗
22. A SANS investigation of the irradiation-enhanced α-α′ phases separation in 7-12 Cr martensitic steels10.1016/S0022-3115(02)01630-6 ↗
23. Atomic scale analysis and phase separation understanding in a thermally aged Fe-20 at.%Cr alloy10.1016/j.jnucmat.2008.10.008 ↗
24. Jaquet · 2000
25. Heintze · 2013
26. Chen · 2014
27. Kinetics of α′ precipitation in an electron-irradiated Fe15Cr alloy10.1016/j.scriptamat.2016.05.021 ↗
28. Cr precipitation in neutron irradiated industrial purity Fe-Cr model alloys10.1016/j.jnucmat.2012.07.021 ↗
29. Microstructural evolution of Fe-22%Cr model alloy under thermal ageing and ion irradiation conditions studied by atom probe tomography10.1016/j.jnucmat.2016.05.007 ↗
30. Estimation of the solubility limit of Cr in Fe at 300 °Cfrom small-angle neutron scattering in neutron-irradiated Fe-Cr alloys10.1016/j.scriptamat.2009.08.028 ↗
31. Atom probe study of irradiation-enhanced α′ precipitation in neutron-irradiated Fe-Cr model alloys10.1016/j.jnucmat.2015.04.005 ↗
32. Some aspects of 475°C embrittlement in Fecralloy steel
33. Precipitation in iron-chromium-aluminum alloys
34. Mapping of 475C embrittlement in ferritic Fe-Cr-Al alloys10.1016/j.scriptamat.2010.08.015 ↗
35. Phase separation in PM 2000TM Fe-base ODS alloy: experimental study at the atomic level10.1016/j.msea.2008.01.029 ↗
36. Aluminum partitioning during phase separation in Fe-20%Cr-6%Al ODS alloy10.1007/s10853-007-2228-z ↗
37. Phase separation kinetics in a Fe-Cr-Al alloy10.1016/j.actamat.2012.05.022 ↗
38. Experimental observations in support of the dynamic-segregation theory to explain the reactive-element effect10.1007/BF01046818 ↗
39. Method for analyzing passive SiC thermometry with a continuous dilatometer to determine irradiation temperature10.1016/j.nimb.2016.01.005 ↗
40. Field · 2015
41. Atom probe specimen preparation with a dual beam SEM/FIB miller10.1016/j.ultramic.2007.02.023 ↗
42. LAMDA: irradiated-materials microscopy at Oak Ridge National Laboratory10.1017/S1431927615005814 ↗
43. A procedure for quantification of precipitate microstructures from three-dimensional atom probe data10.1016/S0304-3991(02)00319-4 ↗
44. Aspects of the observation of clusters in the 3-dimensional atom probe10.1002/sia.2486 ↗
45. New techniques for the analysis of fine-scaled clustering phenomena within atom probe tomography (APT) data10.1017/S1431927607070900 ↗
46. Applications of atom-probe tomography to the characterisation of solute behaviours10.1016/j.mser.2010.05.001 ↗
47. Quantitative atom probe tomography characterization of microstructures in a proton irradiated 304 stainless steel10.1016/j.jnucmat.2014.03.034 ↗
48. Comparison of compositional and morphological atom-probe tomography analyses for a multicomponent Fe-Cu steel10.1017/S1431927607070675 ↗
49. Orientation relationships and interface structure of α-Cr nanoclusters embedded in α-Fe matrix after α-α’ demixing in neutron irradiated oxide dispersion strengthened material10.1016/j.matlet.2012.01.115 ↗
50. The 40 m general purpose small-angle neutron scattering instrument at Oak Ridge National Laboratory10.1107/S0021889812027057 ↗
51. Larson · 2013
52. Ludwig · 1989
53. Gault · 2012
54. Analysis of three-dimensional atom-probe data by the proximity histogram10.1007/S100050010051 ↗
55. Influence of recrystallization on phase separation kinetics of oxide dispersion strengthened Fe-Cr-Al alloy10.1016/j.scriptamat.2011.11.003 ↗
56. New computational method in the theory of spinodal decomposition10.1103/PhysRevA.11.1417 ↗
57. SANS investigation of a neutron-irradiated Fe-9 at%Cr alloy10.1016/j.jnucmat.2010.07.005 ↗
58. SANS investigation of microstructure evolution in high chromium ODS steels after thermal ageing10.1016/j.jnucmat.2012.12.016 ↗
59. Analysis of small-angle scattering data from colloids and polymer solutions: modeling and least-squares fitting10.1016/S0001-8686(97)00312-6 ↗
60. Determination of size distributions from small-angle scattering data for systems with effective hard-sphere interactions10.1107/S0021889893013810 ↗
61. Small-angle scattering from precipitates: analysis by use of a polydisperse hard-sphere model10.1103/PhysRevB.47.657 ↗
62. Small-angle scattering from a commercial Al-Li alloy10.1080/01418618908213869 ↗
63. Characterization of neutron-irradiated ferritic model alloys and a RPV steel from combined APT, SANS, TEM and PAS analyses10.1016/j.jnucmat.2009.12.021 ↗
64. Uncertainties and assumptions associated with APT and SANS characterisation of irradiation damage in RPV steels10.1016/j.jnucmat.2013.07.029 ↗
65. Atom probe tomography of reactor pressure vessel steels: an analysis of data integrity10.1016/j.ultramic.2010.12.033 ↗
66. Identification of the precipitate accompanying 885°F embrittlement in chromium steels
67. Microstructural changes in a neutron-irradiated Fe-15at.%Cr alloy10.1016/j.jnucmat.2014.08.026 ↗
68. Microstructural changes in a neutron-irradiated Fe-6at.%Cr alloy10.1016/j.jnucmat.2014.06.050 ↗
69. Microstructural evolution of ferritic-martensitic steels irradiated in the fast breeder reactor Phénix10.1016/0022-3115(93)90080-I ↗
70. Work-hardening and work-softening of face-centred cubic metal crystals10.1080/14786435708243823 ↗
71. The relationship between hardness and yield stress in irradiated austenitic and ferritic steels10.1016/j.jnucmat.2004.09.024 ↗
72. Influence of nanovoids on α-α′ phase separation in FeCrAl oxide dispersion strengthened alloy
73. Ostwald ripening in multicomponent alloys10.1016/0956-716X(93)90191-T ↗
74. Ostwald ripening in ternary alloys10.1007/BF02649761 ↗
75. The kinetics of precipitation from supersaturated solid solutions10.1016/0022-3697(61)90054-3 ↗
76. Theorie der alterung von niederschlägen durch umlösen
77. Homogeneous second-phase precipitation
78. Ratke · 2002
79. Modelling the overlap of nucleation, growth and coarsening during precipitation10.1016/j.actamat.2004.06.024 ↗