Void swelling and microstructure evolution at very high damage level in self-ion irradiated ferritic-martensitic steels
Source abstract
Abstract
Abstract The void swelling and microstructure evolution of ferritic-martensitic alloys HT9, T91 and T92 were characterized following irradiation with Fe ++ ions at 460 °C to damage levels of 75–650 displacements per atom with 10 atom parts per million pre-implanted helium. Steady state swelling rate of 0.033%/ dpa was determined for HT9, the least swelling resistant alloy, and 0.007%/ dpa in T91. In T91, resistance was due to suppression of void nucleation. Swelling resistance was greatest in T92, with a low density (∼1 × 10 20 m −3 ) of small voids that had not grown appreciably, indicating suppression of nucleation and growth. Additional heats of T91 indicated that alloy composition was not the determining factor of swelling resistance. Carbon and chromium-rich M 2 X precipitates formed at 250 dpa and were correlated with decreased nucleation in T91 and T92, but did not affect void growth in HT9. Dislocation and G-phase microstructure evolution was analyzed up to 650 dpa in HT9.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Hydrogen embrittlement and corrosion behaviors in metals
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (45)
Show source-provided references
1. Traveling-wave reactors: a truly sustainable and full-scale resource for global energy needs
2. Emulation of reactor irradiation damage using ion beams10.1016/j.scriptamat.2014.06.003 ↗
3. Effect of pre-implanted helium on void swelling evolution in self-ion irradiated HT910.1016/j.jnucmat.2015.01.045 ↗
4. Effect of irradiation mode on the microstructure of self-ion irradiated ferritic-martensitic alloys10.1016/j.jnucmat.2015.05.016 ↗
5. Void swelling in high dose ion-irradiated reduced activation ferritic–martensitic steels10.1016/j.jnucmat.2015.03.050 ↗
6. Void swelling in ferritic-martensitic steels under high dose ion irradiation: exploring possible contributions to swelling resistance
7. Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa10.1016/j.jnucmat.2014.06.011 ↗
8. Irradiation creep and void swelling of two LMR heats of HT9 at ∼400 C and 165 dpa10.1016/S0022-3115(96)00413-8 ↗
9. Variability of irradiation creep and swelling of HT9 irradiated to high neutron fluence at 400-600C
10. Irradiation creep and swelling of the US fusion heats of HT9 and 9Cr-1Mo to 208 dpa at - 400C10.1016/0022-3115(94)90131-7 ↗
11. Microstructural examination of commercial ferritic alloys at 200 dpa10.1016/S0022-3115(96)00222-X ↗
12. Microstructural analysis of neutron-irradiated martensitic steels10.1016/0022-3115(96)00165-1 ↗
13. Microstructural stability of an HT-9 fuel assembly duct irradiated in FFTF10.1016/j.jnucmat.2011.03.050 ↗
14. Microstructural analysis of an HT9 fuel assembly duct irradiated in FFTF to 155dpa at 443°C10.1016/j.jnucmat.2009.06.010 ↗
15. SANS and TEM of ferritic-martensitic steel T91 irradiated in FFTF up to 184 dpa at 413 °c10.1016/j.jnucmat.2013.04.025 ↗
16. Microstructure of 9 Cr-1 MoVNb steel irradiated to 36 dpa at elevated temperatures in HFIR10.1016/0022-3115(84)90606-8 ↗
17. Swelling behavior of commercial alloys, EM-12 and HT-9, as assessed by heavy ion bombardment
18. Suppression of void nucleation by injected interstitials during heavy ion bombardment10.1016/0022-3115(84)90062-X ↗
19. Dual-ion irradiation: impact of the conflicting roles of helium on void nucleation
20. Effect of self-ion injection in simulation studies of void swelling10.1016/0022-3115(77)90194-5 ↗
21. 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 ↗
22. Thermal annealing recovery of fracture toughness in HT9 steel after irradiation to high doses10.1016/j.jnucmat.2013.07.064 ↗
23. Klueh · 2001
24. SRIM – the stopping and range of ions in matter10.1016/j.nimb.2010.02.091 ↗
25. In situ lift-out using a FIB-SEM system10.1016/j.micron.2004.03.002 ↗
26. Effect of defect imbalance on void swelling distributions produced in pure iron irradiated with 3.5MeV self-ions10.1016/j.jnucmat.2014.06.002 ↗
27. Characterization of the intermetallic G-phase in an AISI 329 duplex stainless steel10.1023/A:1018669217124 ↗
28. Radiation damage studies of the 10 to 13% chromium-containing steels and alloys irradiated with heavy ions
29. Methodology for determining void swelling at very high damage under ion irradiation10.1016/j.jnucmat.2016.05.026 ↗
30. Microstructural evolution of ferritic-martensitic steels irradiated in the fast breeder reactor Phénix10.1016/0022-3115(93)90080-I ↗
31. Microstructural changes and void swelling of a 12Cr ODS ferritic-martensitic alloy after high-dpa self-ion irradiation10.1016/j.jnucmat.2015.09.016 ↗
32. Void swelling in binary FeCr alloys at 200 dpa10.1016/0022-3115(95)00053-4 ↗
33. Swelling and dislocation evolution in simple ferritic alloys irradiated to high fluence in FFTF/MOTA Fe-3Cr I Fe-12Cr Fe-15Cr10.1016/0022-3115(94)00669-5 ↗
34. Jiao · Precipitate evolution in ion-irradiated HCM12A. J. Nucl. Mater. · 2012 · 425 · 105
35. Was · 2007
36. Phase stability of an HT-9 duct irradiated in FFTF10.1016/j.jnucmat.2012.06.038 ↗
37. Formation and stability of radiation-induced phases in neutron-irradiated austenitic and ferritic steels10.1016/0022-3115(89)90525-4 ↗
38. Influence of high dose neutron irradiation on microstructure of EP-450 ferritic–martensitic steel irradiated in three Russian fast reactors10.1016/j.jnucmat.2004.04.309 ↗
39. Void swelling in irons and ferritic steels I. Mechanisms of swelling suppression10.1016/0022-3115(79)90122-3 ↗
40. Void-swelling in irons and ferritic steels II. An experimental survey of materials irradiated in a fast reactor10.1016/0022-3115(79)90123-5 ↗
41. Suppression of void nucleation by a vacancy trapping mechanism10.1016/0036-9748(73)90102-6 ↗
42. Void-swelling in fv607 ferritic steel- II. A Theoretic Model10.1016/0022-3115(78)90544-5 ↗
43. The effects of impurity trapping on irradiation-induced swelling and creep10.1016/0022-3115(78)90362-8 ↗
44. 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 ↗
45. High temperature radiation damage phenomena in complex alloys10.1016/0022-3115(82)90500-1 ↗