journal article·2020-02

The effects of loop size on the unfaulting of Frank loops in heavy ion irradiation

Dongyue Chen, Kenta Murakami, Kenji Dohi, Kenji Nishida, Zhengcao Li, Naoto Sekimura

Publisher page

Abstract

Abstract When stainless steels are exposed to high irradiation dose, a fraction of Frank loops will unfault and transform into perfect loops. After unfaulting, perfect loops can glide and impinge into other loops to form dislocation networks, and dislocation networks will act as sinks for point defects and solute elements. Besides, unfaulting will influence the extent of irradiation hardening as well. Based on previous theories, the size of Frank loops was considered to be a key factor in unfaulting. To better understand the unfaulting process, 316L stainless steel model alloy was irradiated to 5dpa at 350 °C, 400 °C and 450 °C by 3 MeV Ni ions. Method was developed to quantitatively compare the size and density between Frank loops and perfect loops through relrod and weak-beam dark field techniques. Results showed that unfaulting barely occurred at 350 °C but was distinct at 400 °C and 450 °C. The majority of perfect loops were in the size range of 8–16 nm at 400 °C and were in the size range of 12–20 nm at 450 °C. The existence of a critical loop size for unfaulting was not supported by our results. Moreover, by our results, the energy of Frank loops does not play a decisive role in unfaulting, and the simple approximation of geometric constraint in the rate theory to calculate unfaulting diameter needs to be revisited. Irradiation hardening was also analyzed by nano-indention. It was found that loop unfaulting played an important role in the hardening decrease from 350 °C to 450 °C.
Source: openaire · Quality: candidate unverified · Source record ↗

Research context

OpenAlex topics: Fusion materials and technologies · Microstructure and mechanical properties · Ion-surface interactions and analysis

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

References (39)

Show source-provided references
1. IAEA · 2007
2. Overview of microstructural evolution in neutron-irradiated austenitic stainless-steels10.1016/0022-3115(93)90077-C ↗
3. Influence of irradiation temperature and dose gradients on the microstructural evolution in neutron-irradiated 316SS10.1016/S0022-3115(03)00003-5 ↗
4. Effects of dose rate on microsturctural evolution and swelling in austenitic steels under irradiation10.1016/S0022-3115(00)00355-X ↗
5. The evolution of mechanical property change in irradiated austenitic stainless-steels10.1016/0022-3115(93)90129-M ↗
6. Stability of vacancy clusters in metals .1. Energy calculations for pure metals10.1080/01418618708209803 ↗
7. On the origin of deformation microstructures in austenitic stainless steel: Part II - Mechanisms10.1016/S1359-6454(01)00194-X ↗
8. In situ deformation and unfaulting of interstitial loops in proton-irradiated steels10.1080/01418619208205606 ↗
9. Dose dependence of the microstructural evolution in neutron-irradiated austenitic stainless-steel10.1016/0022-3115(93)90128-L ↗
10. Molecular dynamics simulation of screw dislocations interacting with interstitial frank loops in a model FCC crystal10.1016/j.actamat.2003.09.044 ↗
11. Atomic-scale plasticity in the presence of Frank loops10.1080/14786430601011497 ↗
12. Effects of stacking fault energies on the interaction between an edge dislocation and an 8.0-nm-diameter Frank loop of self-interstitial atoms10.1016/j.nme.2016.10.010 ↗
13. Evolution of fine-scale defects in stainless steels neutron-irradiated at 275 degrees C10.1016/S0022-3115(03)00002-3 ↗
14. Microstructural evolution in annealed austenitic steels during neutron-irradiation10.1179/095066087790150331 ↗
15. Investigation of interactions between defect clusters in stainless steels by in situ irradiation at elevated temperatures10.1016/j.actamat.2018.10.011 ↗
16. Depth distribution of Frank loop defects formed in ion-irradiated stainless steel and its dependence on Si addition10.1016/j.nimb.2015.08.029 ↗
17. The synergistic influence of temperature and displacement rate on microstructural evolution of ion-irradiated Fe-15Cr-16Ni model austenitic alloy10.1016/j.jnucmat.2007.03.061 ↗
18. Silicons role in determining swelling in neutron-irradiated Fe-Ni-Cr-Si alloys10.1016/0022-3115(92)90673-9 ↗
19. Improvement of the high fluence irradiation facility at the university of Tokyo10.1016/j.nimb.2016.05.022 ↗
20. Ziegler
21. 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 ↗
22. Dislocation loop evolution under ion irradiation in austenitic stainless steels10.1016/j.jnucmat.2010.02.009 ↗
23. Evolution of microstructure and microchemistry in cold-worked 316 stainless steels under PWR irradiation10.1080/18811248.2006.9711078 ↗
24. Effects of stacking fault energies on formation of irradiation-induced defects at various temperatures in face-centred cubic metals10.1080/14786435.2018.1515507 ↗
25. Effects of stacking fault energy on defect formation process in face-centered cubic metals10.1080/14786435.2016.1171415 ↗
26. Influence of stacking fault energies on the size distribution and character of defect clusters formed by collision cascades in face-centered cubic metals10.1016/j.nme.2016.07.008 ↗
27. MD simulations to evaluate effects of applied tensile strain on irradiation-induced defect production at various PKA energies10.1016/j.fusengdes.2012.03.012 ↗
28. Was · 2007
29. Evaluation of irradiation hardening of proton irradiated stainless steels by nanoindentation10.1016/j.jnucmat.2013.12.009 ↗
30. The relationship between hardness and yield stress in irradiated austenitic and ferritic steels10.1016/j.jnucmat.2004.09.024 ↗
31. Elevated temperature irradiation damage in CANDU spacer material Inconel X-75010.1016/j.jnucmat.2013.11.008 ↗
32. Effects of proton irradiation on the microstructure and microchemistry of type-304l stainless-steel10.1016/0022-3115(93)90101-4 ↗
33. Defect accumulation in jpca and its high-purity model alloys irradiated with D-T neutrons10.1016/0022-3115(88)90421-7 ↗
34. Tailoring plasticity of austenitic stainless steels for nuclear applications: review of mechanisms controlling plasticity of austenitic steels below 400 degrees C10.1016/j.jnucmat.2016.04.015 ↗
35. Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals10.1016/S0022-3115(99)00075-6 ↗
36. The primary origin of dose rate effects on microstructural evolution of austenitic alloys during neutron irradiation10.1016/S0022-3115(02)01202-3 ↗
37. Effects of titanium additions to austenitic ternary alloys on microstructural evolution and void swelling10.1080/14786430412331331871 ↗
38. Influence of carbon addition on neutron-induced void swelling of Fe-l5Cr-16Ni-0.25Ti model alloy10.1016/j.jnucmat.2007.03.065 ↗
39. Microstructural evolution in an austenitic stainless-steel fusion-reactor 1st-wall10.1016/0022-3115(86)90067-X ↗