Atom probe tomography characterization of high-dose ion irradiated MA957
Source abstract
Abstract
Abstract Because the microstructure of oxide dispersion strengthened (ODS) alloys largely determines its mechanical properties in nuclear reactors, it is critical to understand the irradiation response of microstructure after high-dose radiation damage for safety and performance concerns. This paper presents a comprehensive characterization of microstructural responses to ion irradiation of the ODS ferritic alloy MA957 using atom probe tomography and compares the observations to current theories on mechanisms for microstructural evolution during irradiation. The MA957 specimens were irradiated by 1.8 MeV Cr3+ ions to doses and at temperatures relevant to advanced fast reactors (100 dpa and 500 dpa at 400–500°C). The stability of YTiO particles, formation of alpha prime (α′), and radiation-induced segregation were quantified and analyzed. The results show that the evolution of YTiO particles with respect to dose and temperature is consistent with the Nelson-Hudson-Mazey rate theory model that considers the competing effects of recombination and ballistic dissolution. The formation of Cr-rich precipitates (αʹ) was observed in specimens irradiated at temperatures up to 450°C, and it shows a strong dependence on temperature. Irradiation-induced segregation on grain boundaries was investigated in the 100 dpa specimens. In addition to the commonly studied element Cr, this study also analyzed segregation of Y and Ti. While the magnitude of segregation varies due to intrinsic variability of grain boundary character, clear trends with respect to irradiation temperature were observed. Overall, these results revealed relatively small but distinct effects of irradiation on microstructure evolution to 100 or 500 dpa, demonstrating the excellent radiation tolerance of ODS alloys.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Advanced Materials Characterization Techniques
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (92)
Show source-provided references
1. Emulation of reactor irradiation damage using ion beams10.1016/j.scriptamat.2014.06.003 ↗
2. Recent developments in irradiation-resistant steels10.1146/annurev.matsci.38.060407.130315 ↗
3. Irradiation creep and swelling from 400 to 600 C of the oxide dispersion strengthened ferritic alloy MA95710.1016/j.jnucmat.2004.04.296 ↗
4. Theory and experimental background on dimensional changes in irradiated alloys10.1016/0022-3115(94)90009-4 ↗
5. The effects of oxide evolution on mechanical properties in proton-and neutron-irradiated Fe-9% Cr ODS steel10.1016/j.jnucmat.2016.07.022 ↗
6. Analysis of hardening limits of oxide dispersion strengthened steel10.1016/j.jnucmat.2012.07.024 ↗
7. Formulating the Strength Factor α for Improved Predictability of Radiation Hardening10.1016/j.jnucmat.2015.07.009 ↗
8. Response of 14YWT alloys under neutron irradiation: A complementary study on microstructure and mechanical properties10.1016/j.actamat.2019.01.041 ↗
9. Microstructural development of a heavily neutron-irradiated ODS ferritic steel (MA957) at elevated temperature10.1016/j.jnucmat.2007.03.145 ↗
10. Phase stability of oxide dispersion-strengthened ferritic steels in neutron irradiation10.1016/S0022-3115(02)01077-2 ↗
11. Irradiation behavior evaluation of oxide dispersion strengthened ferritic steel cladding tubes irradiated in JOYO10.1016/j.jnucmat.2013.04.051 ↗
12. Nano-cluster stability following neutron irradiation in MA957 oxide dispersion strengthened material10.1016/j.jnucmat.2013.10.010 ↗
13. Structural and chemical matrix evolution following neutron irradiation in a MA957 oxide dispersion strengthened material10.1016/j.jnucmat.2012.11.038 ↗
14. Microstructural investigation of the stability under irradiation of oxide dispersion strengthened ferritic steels10.1016/j.jnucmat.2004.05.018 ↗
15. Irradiation creep and density changes observed in MA957 pressurized tubes irradiated to doses of 40–110dpa at 400–750°C in FFTF10.1016/j.jnucmat.2012.04.005 ↗
16. Atom probe tomography analysis of high dose MA957 at selected irradiation temperatures10.1016/j.jnucmat.2015.01.006 ↗
17. Effect of Ti and Cr on dispersion, structure and composition of oxide nano-particles in model ODS alloys10.1016/j.actamat.2015.06.032 ↗
18. The Stability of 9Cr-ODS Oxide Particles Under Heavy-Ion Irradiation10.13182/NSE05-A2549 ↗
19. Heavy-ion irradiation effects on the morphology of complex oxide particles in oxide dispersion strengthened ferritic steels10.1016/j.jnucmat.2007.03.149 ↗
20. Amorphization of oxides in ODS materials under low and high energy ion irradiations10.1016/j.jnucmat.2011.01.065 ↗
21. In situ TEM study of the stability of nano-oxides in ODS steels under ion-irradiation10.1016/j.jnucmat.2011.12.009 ↗
22. Particle stability in model ODS steel irradiated up to 100dpa at 600°C: TEM and nano-indentation investigation10.1016/j.jnucmat.2012.04.001 ↗
23. Radiation stability of nanoclusters in nano-structured oxide dispersion strengthened (ODS) steels10.1016/j.jnucmat.2012.11.021 ↗
24. Stability of nanoclusters in 14YWT oxide dispersion strengthened steel under heavy ion-irradiation by atom probe tomography10.1016/j.jnucmat.2014.03.024 ↗
25. Microstructural changes and void swelling of a 12Cr ODS ferritic-martensitic alloy after high-dpa self-ion irradiation10.1016/j.jnucmat.2015.09.016 ↗
26. Nanoscale analysis of ion irradiated ODS 14YWT ferritic alloy10.1016/j.jnucmat.2019.151852 ↗
27. Ion irradiation stability of oxide nano-particles in ODS alloys: TEM studies10.1016/j.jnucmat.2019.151861 ↗
28. Stability of nanosized oxides in ferrite under extremely high dose self ion irradiations10.1016/j.jnucmat.2017.01.015 ↗
29. Radiation-induced Ostwald ripening in oxide dispersion strengthened ferritic steels irradiated at high ion dose10.1016/j.actamat.2014.06.060 ↗
30. On the α–α′ miscibility gap of Fe–Cr alloys10.1016/j.scriptamat.2008.08.008 ↗
31. α′ precipitation in neutron-irradiated Fe–Cr alloys10.1016/j.scriptamat.2013.10.001 ↗
32. P.J. Grobner, The 885° f (475°
33. Embrittlement and aging at 475°C in an experimental ferritic stainless steel containing 38 wt.% chromium10.1016/0921-5093(94)09731-3 ↗
34. Embrittlement and hardening during thermal aging of high Cr oxide dispersion strengthened alloys10.1016/j.jnucmat.2007.03.007 ↗
35. Atom probe study of irradiation-enhanced α′ precipitation in neutron-irradiated Fe–Cr model alloys10.1016/j.jnucmat.2015.04.005 ↗
36. Irradiation-enhanced α′ precipitation in model FeCrAl alloys10.1016/j.scriptamat.2016.02.002 ↗
37. Tensile and fracture toughness properties of MA957: implications to the development of nanocomposited ferritic alloys10.1016/S0022-3115(02)01220-5 ↗
38. Fracture toughness and tensile properties of nano-structured ferritic steel 12YWT10.1016/j.jnucmat.2007.03.143 ↗
39. Microstructure and impact properties of ferritic ODS ODM401 (14%Cr-ODS of MA957 type)10.1016/j.jnucmat.2011.01.066 ↗
40. Process development for 9Cr nanostructured ferritic alloy (NFA) with high fracture toughness10.1016/j.jnucmat.2013.10.007 ↗
41. Tensile fracture characteristics of nanostructured ferritic alloy 14YWT10.1016/j.jnucmat.2010.09.054 ↗
42. High temperature fracture characteristics of a nanostructured ferritic alloy (NFA)10.1016/j.jnucmat.2010.09.031 ↗
43. 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 ↗
44. A systematic study of radiation-induced segregation in ferritic–martensitic alloys10.1016/j.jnucmat.2013.07.071 ↗
45. Assessment of radiation-induced segregation mechanisms in austenitic and ferritic–martensitic alloys10.1016/j.jnucmat.2011.01.031 ↗
46. M.L. Hamilton, D.S. Gelles, R.J. Lobsinger, G.D. Johnson, W.F. Brown, M.M. Paxton, A.J. Puigh, C.R. Eiholzer, C. Martinez, M.A. Blotter, Fabrication Technological Development of the Oxide Dispersion Strengthened Alloy MA957 for Fast Reactor Applications, 2000.10.2172/965199 ↗
47. M.L. Hamilton, D.S. Gelles, R.J. Lobsinger, M.M. Paxton, W.F. Brown, Fabrication Technology for ODS alloy MA957, 2000.10.2172/752167 ↗
48. Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500dpa10.1016/j.jnucmat.2014.06.011 ↗
49. On the use of SRIM for computing radiation damage exposure10.1016/j.nimb.2013.05.008 ↗
50. SRIM–The stopping and range of ions in matter (2010), Nuclear Instruments and Methods in Physics Research Section B
51. Modeling injected interstitial effects on void swelling in self-ion irradiation experiments10.1016/j.jnucmat.2015.10.002 ↗
52. 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 ↗
53. Modification of SRIM-calculated dose and injected ion profiles due to sputtering, injected ion buildup and void swelling10.1016/j.nimb.2016.09.015 ↗
54. Modeling the impact of radiation-enhanced diffusion on implanted ion profiles10.1016/j.jnucmat.2018.06.042 ↗
55. Carbon Contamination During Ion Irradiation - Accurate Detection and Characterization of its Effect on Microstructure of Ferritic/Martensitic Steels10.1038/s41598-017-15669-y ↗
56. Carbon Contamination, Its Consequences and Its Mitigation in Ion-Simulation of Neutron-Induced Swelling of Structural Metals
57. Standardization of accelerator irradiation procedures for simulation of neutron induced damage in reactor structural materials10.1016/j.nimb.2017.05.026 ↗
58. Impact of composition modification induced by ion beam Coulomb-drag effects on the nanoindentation hardness of HT910.1016/j.nimb.2018.12.051 ↗
59. In situ site-specific specimen preparation for atom probe tomography10.1016/j.ultramic.2006.06.008 ↗
60. Efficient sampling for three-dimensional atom probe microscopy data10.1016/S0304-3991(02)00317-0 ↗
61. The Application of the OPTICS Algorithm to Cluster Analysis in Atom Probe Tomography Data10.1017/S1431927618015386 ↗
62. Crystallographic structural analysis in atom probe microscopy via 3D Hough transformation10.1016/j.ultramic.2010.11.018 ↗
63. Atom probe crystallography: Characterization of grain boundary orientation relationships in nanocrystalline aluminium10.1016/j.ultramic.2010.11.014 ↗
64. Chromatic aberrations in the field evaporation behavior of small precipitates10.1017/S1431927608080793 ↗
65. A review of the irradiation evolution of dispersed oxide nanoparticles in the b.c.c. Fe-Cr system: Current understanding and future directions10.1016/j.jnucmat.2017.01.009 ↗
66. The stability of precipitates in an irradiation environment10.1016/0022-3115(72)90043-8 ↗
67. 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 ↗
68. Stability of non-stoichiometric clusters in the MA957 ODS ferrtic alloy10.1016/j.jnucmat.2010.12.056 ↗
69. Nanoscale characterisation of ODS–Eurofer 97 steel: An atom-probe tomography study10.1016/j.jnucmat.2010.02.007 ↗
70. A comparison between different oxide dispersion strengthened ferritic steel ongoing in situ oxide dissolution in High Voltage Electron Microscope10.1016/j.jnucmat.2012.03.011 ↗
71. Radiation induced segregation in quaternary Fe-Ti-Y-O alloys10.1016/j.jallcom.2017.01.017 ↗
72. On the remarkable thermal stability of nanostructured ferritic alloys10.1016/j.msea.2014.06.097 ↗
73. Microstructural evolution of ferritic-martensitic steels irradiated in the fast breeder reactor Phénix10.1016/0022-3115(93)90080-I ↗
74. Spinodal decomposition in the Fe−Cr system10.1007/BF02913370 ↗
75. Barkar · 2018 · 56
76. Phase stability under irradiation10.1016/0079-6425(84)90001-X ↗
77. Two-band modeling of $\ensuremath{\alpha}$-prime phase formation in Fe-Cr10.1103/PhysRevB.72.214119 ↗
78. Accelerator to Accelerator Differences in Radiation Response of HT-9
79. High Dose ion Irradiation of a 9Cr Tempered Ferritic/Martensitic Steel
80. Behaviour of P, Si, Ni impurities and Cr in self ion irradiated Fe–Cr alloys – Comparison to neutron irradiation10.1016/j.jnucmat.2014.10.024 ↗
81. Dose rate dependence of Cr precipitation in an ion-irradiated Fe18Cr alloy10.1016/j.scriptamat.2017.11.040 ↗
82. Kinetics of α′ precipitation in an electron-irradiated Fe15Cr alloy10.1016/j.scriptamat.2016.05.021 ↗
83. α′ precipitation in neutron-irradiated Fe–Cr alloys10.1016/j.scriptamat.2013.10.001 ↗
84. 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 ↗
85. α' formation kinetics and radiation induced segregation in neutron irradiated 14YWT nanostructured ferritic alloys10.1038/s41598-019-44508-5 ↗
86. Irradiation-induced grain boundary chromium microchemistry in high alloy ferritic steels10.1016/j.scriptamat.2008.01.004 ↗
87. Dependence on grain boundary structure of radiation induced segregation in a 9wt.% Cr model ferritic/martensitic steel10.1016/j.jnucmat.2012.12.026 ↗
88. The mechanism of radiation-induced segregation in ferritic-martensitic steels
89. 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 ↗
90. Response of 9Cr-ODS steel to proton irradiation at 400°C10.1016/j.jnucmat.2014.05.004 ↗
91. Grain boundary segregation in an oxide-dispersion-strengthened ferritic steel10.1007/BF00277989 ↗
92. Influences of interstitial and extrusion temperature on grain boundary segregation, Y−Ti−O nanofeatures, and mechanical properties of ferritic steels10.1016/j.actamat.2018.04.046 ↗