journal article·2016-09Open access

Temperature dependent dispersoid stability in ion-irradiated ferritic-martensitic dual-phase oxide-dispersion-strengthened alloy: Coherent interfaces vs. incoherent interfaces

Tianyi Chen, Jonathan G. Gigax, Lloyd Price, Di Chen, S. Ukai, Eda Aydogan, S.A. Maloy, F.A. Garner, Lin Shao

Acta Materialia· Volume 116

Abstract

Abstract In this study, the microstructure of a 12Cr ferritic-martensitic oxide-dispersion-strengthened (ODS) alloy is studied before and after Fe ion irradiation up to 200 peak displacements per atom (dpa). Irradiation temperature ranges from 325 to 625 °C. Before irradiation, both coherent and incoherent dispersoids exist in the matrix. In response to irradiation, the mean sizes of dispersoids in both the ferrite and tempered martensite phases change to equilibrium values that increase with irradiation temperature. The evolution of dispersoids under irradiation is explained by a competition between athermal-radiation-driven shrinkage and thermal-diffusion-driven growth, with interface coherency affecting the growth mechanism. However, each coherency type exhibits different evolution behavior under irradiation. Coherent dispersoids, regardless of their initial size, change toward an equilibrium size at each temperature tested. On the other hand, incoherent dispersoids are destroyed at lower test temperatures but survive while shrinking in size at higher temperatures. This difference in behavior can be explained by the lower interfacial energy of coherent dispersoids in comparison with incoherent dispersoids. This study sheds light on the roles of interface configurations in maintaining dispersoid integrity under irradiation.
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 (80)

Show source-provided references
1. Materials challenges in nuclear energy10.1016/j.actamat.2012.11.004 ↗
2. Structural materials for fission and fusion energy10.1016/S1369-7021(09)70294-9 ↗
3. Ferritic/martensitic steels for next-generation reactors10.1016/j.jnucmat.2007.05.005 ↗
4. Irradiation performance of cladding and structural steels in liquid metal reactors
5. Materials needs for fusion, Generation IV fission reactors and spallation neutron sources – similarities and differences10.1016/j.jnucmat.2004.04.016 ↗
6. Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure10.1016/S0022-3115(99)00225-1 ↗
7. Use of self-ion bombardment to study void swelling in advanced radiation-resistant alloys
8. Compositional and temperature dependence of void swelling in model Fe-Cr base alloys irradiated in the EBR-II fast reactor10.1016/S0022-3115(00)00338-X ↗
9. Microstructural evolution of ferritic-martensitic steels irradiated in the fast breeder reactor Phénix10.1016/0022-3115(93)90080-I ↗
10. Response of equal channel angular extrusion processed ultrafine-grained T91 steel subjected to high temperature heavy ion irradiation10.1016/j.actamat.2014.04.034 ↗
11. Chen · 2013 · vol. 3
12. Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa10.1016/j.jnucmat.2014.06.011 ↗
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. Recent developments in irradiation-resistant steels10.1146/annurev.matsci.38.060407.130315 ↗
15. Helium effects on creep properties of Fe-14CrWTi ODS steel at 650 °C10.1016/j.jnucmat.2014.07.010 ↗
16. Dislocation loops and bubbles in oxide dispersion strengthened ferritic steel after helium implantation under stress10.1016/j.actamat.2007.09.016 ↗
17. Recent progress in developing and qualifying nanostructured ferritic alloys for advanced fission and fusion applications10.1007/s11837-014-1207-5 ↗
18. Irradiation response of ODS ferritic steels to high-energy Ne ions at HIRFL10.1016/j.jnucmat.2014.04.015 ↗
19. Nano-mesoscopic structure control in 9Cr-ODS ferritic steels10.1179/174892407X210357 ↗
20. Radiation response of a 9 chromium oxide dispersion strengthened steel to heavy ion irradiation10.1016/j.jnucmat.2007.11.001 ↗
21. Radiation effects on the microstructure of a 9Cr-ODS alloy10.1007/s11837-008-0003-5 ↗
22. Residual ferrite formation in 12CrODS steels10.1016/j.jnucmat.2014.09.038 ↗
23. Stability of nanoclusters in 14YWT oxide dispersion strengthened steel under heavy ion-irradiation by atom probe tomography10.1016/j.jnucmat.2014.03.024 ↗
24. Microstructural investigation of the stability under irradiation of oxide dispersion strengthened ferritic steels10.1016/j.jnucmat.2004.05.018 ↗
25. Microstructural development of a heavily neutron-irradiated ODS ferritic steel (MA957) at elevated temperature10.1016/j.jnucmat.2007.03.145 ↗
26. Nano-oxide particle stability of 9-12Cr grain morphology modified ODS steels under neutron irradiation10.1016/j.jnucmat.2004.04.041 ↗
27. Radiation-induced Ostwald ripening in oxide dispersion strengthened ferritic steels irradiated at high ion dose10.1016/j.actamat.2014.06.060 ↗
28. Characterization and in-situ ion-irradiation of MA957 ODS steel
29. Amorphization of oxides in ODS materials under low and high energy ion irradiations10.1016/j.jnucmat.2011.01.065 ↗
30. Radiation stability of the ODS alloys against swift heavy ion impact10.1016/j.jnucmat.2013.07.017 ↗
31. Microstructural changes of neutron irradiated ODS ferritic and martensitic steels10.1016/j.jnucmat.2004.04.133 ↗
32. Heavy-ion irradiation effects on the morphology of complex oxide particles in oxide dispersion strengthened ferritic steels10.1016/j.jnucmat.2007.03.149 ↗
33. Stability of Y-Ti complex oxides in Fe-16Cr-0.1Ti ODS ferritic steel before and after heavy-ion irradiation10.1016/j.jnucmat.2008.12.169 ↗
34. Microstructural stability of a self-ion irradiated lanthana-bearing nanostructured ferritic steel10.1016/j.jnucmat.2015.03.040 ↗
35. ASTM E521 · 2009
36. The influence of beam rastering on the swelling of self-ion irradiated pure iron at 450 °C10.1016/j.jnucmat.2015.05.025 ↗
37. Effect of irradiation mode on the microstructure of self-ion irradiated ferritic-martensitic alloys10.1016/j.jnucmat.2015.05.016 ↗
38. SRIM – the stopping and range of ions in matter10.1016/j.nimb.2010.02.091 ↗
39. Greenwood · 1985
40. On the use of SRIM for computing radiation damage exposure10.1016/j.nimb.2013.05.008 ↗
41. Reverse phase transformation from alpha to gamma in 9Cr-ODS ferritic steels10.1016/j.jnucmat.2010.12.250 ↗
42. Response of nanoclusters in a 9Cr ODS steel to 1dpa, 525 °C proton irradiation10.1016/j.jnucmat.2010.07.002 ↗
43. Formation of Y2O3 nanoclusters in nano-structured ferritic alloys: modeling of precipitation kinetics and yield strength10.1016/j.jnucmat.2010.04.020 ↗
44. Effect of elastic interaction energy on coarsening of γ′ precipitates in a mechanically alloyed ODS Ni-base superalloy10.1023/A:1004461724568 ↗
45. Microstructural examination of commercial ferritic alloys at 200 dpa10.1016/S0022-3115(96)00222-X ↗
46. Microstructure of irradiated ferritic/martensitic steels in relation to mechanical properties10.1016/S0022-3115(02)01034-6 ↗
47. Microstructural development under irradiation in European ODS ferritic/martensitic steels10.1016/j.jnucmat.2006.02.005 ↗
48. Helium effects on void formation in 9Cr-1MoVNb and 12Cr-1MoVW irradiated in HFIR10.1016/0022-3115(86)90120-0 ↗
49. Phase stability of an HT-9 duct irradiated in FFTF10.1016/j.jnucmat.2012.06.038 ↗
50. Nano-cluster stability following neutron irradiation in MA957 oxide dispersion strengthened material10.1016/j.jnucmat.2013.10.010 ↗
51. 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 ↗
52. Impact of the injected interstitial on the correlation of charged particle and neutron-induced radiation damage10.1016/0022-3115(83)90023-5 ↗
53. Was · 2007
54. Perspective of ODS alloys application in nuclear environments10.1016/S0022-3115(02)01043-7 ↗
55. Characterization of high temperature creep properties in recrystallized 12Cr–ODS ferritic steel claddings10.1080/18811248.2002.9715271 ↗
56. Effect of yttria particle size on the microstructure and compression creep properties of nanostructured oxide dispersion strengthened ferritic (Fe-12Cr-2W-0.5Y2O3) alloy10.1016/j.msea.2011.02.078 ↗
57. Pinning of dislocations on the departure side of strengthening dispersoids10.1016/0036-9748(83)90333-2 ↗
58. The threshold stress and departure side pinning of dislocations by dispersoids10.1016/0001-6160(84)90097-X ↗
59. Structural changes of tempered martensitic 9%Cr-2%W-3%Co steel during creep at 650 °C10.1016/j.msea.2011.12.020 ↗
61. The effect of oxide particle coherency on Zener pinning in ODS superalloys10.1007/BF00278146 ↗
62. Mechanical properties of Y2Ti2O710.1016/j.scriptamat.2010.11.042 ↗
63. Synchrotron study on load partitioning between ferrite/martensite and nanoparticles of a 9Cr ODS steel10.1016/j.jnucmat.2014.06.060 ↗
64. The interfacial orientation relationship of oxide nanoparticles in a hafnium-containing oxide dispersion-strengthened austenitic stainless steel10.1016/j.matchar.2015.01.015 ↗
65. Effects of extrusion temperature on the nano-mesoscopic structure and mechanical properties of an Al-alloyed high-Cr ODS ferritic steel10.1016/j.jnucmat.2011.01.061 ↗
66. On the coherency of Y2Ti2O7 particles with austenitic matrix of oxide dispersion strengthened steel10.1016/j.actamat.2015.01.060 ↗
67. Interfacial strained structure and orientation relationships of the nanosized oxide particles deduced from elasticity-driven morphology in oxide dispersion strengthened materials10.1016/j.actamat.2011.09.042 ↗
68. Porter · 2006
69. Howe · 1997
70. Balluffi · 2005
71. Ukai · 2011
72. Effect of matrix recrystallization on morphology, crystallography and coarsening behavior of vanadium carbide in austenite10.1016/j.actamat.2004.04.027 ↗
73. Response of nanostructured ferritic alloys to high-dose heavy ion irradiation10.1016/j.jnucmat.2013.11.002 ↗
74. Theory of the ageing of precipitates by redissolution (Ostwald maturing)
75. Modelling the overlap of nucleation, growth and coarsening during precipitation10.1016/j.actamat.2004.06.024 ↗
76. Gibbs-Thomson effects in phase transformations10.1016/j.scriptamat.2004.12.026 ↗
77. Influence of the low interfacial density energy on the coarsening resistivity of the nano-oxide particles in Ti-added ODS material10.1016/j.jnucmat.2012.10.051 ↗
78. The stability of precipitates in an irradiation environment10.1016/0022-3115(72)90043-8 ↗
79. Phase instability under irradiation10.1016/0079-6425(84)90001-X ↗
80. Comment on Fe-Y (Iron-Yttrium)