Combining mesoscale thermal transport and x-ray diffraction measurements to characterize early-stage evolution of irradiation-induced defects in ceramics
Source abstract
Abstract
In situ characterization of defects, microstructure, and properties will provide new perspectives regarding the structure-property relationship of materials in extreme environments. In this communication, we investigate the utility of laser-based thermal transport measurements in combination with X-ray diffraction as a means to characterize the early-stage evolution of irradiation-induced defects in ceramics. Uranium dioxide is used as a model system to analyze the impact of irradiation-induced defects with 2.6 MeV H and 3.9 MeV He ions up to a dose of 0.1 displacement per atom (dpa) at low temperature. For these radiation regimes, the formation of extended defects such as loops and voids is limited as compared to point defects. Lattice expansion was determined from X-ray diffraction analysis. Modulated thermoreflectance was used to measure the thermal conductivity of the ion damaged region. Both H and He irradiation leads to an expansion of the crystal lattice and a reduction in thermal conductivity. For the same dpa, the lattice expansion and conductivity reduction were notably different for H and He irradiated samples. The results were analyzed using simple models for lattice expansion and thermal conductivity reduction, informed by atomistic simulation from the literature. The modeling results suggest that the difference in the defect kinetics between two conditions can be attributed to ionization induced enhanced defect mobility and the stability of Schottky defects. These results demonstrate the utility of thermal conductivity measurements as a tool for characterization of microstructure under irradiation.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear materials and radiation effects · Fusion materials and technologies
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (76)
Show source-provided references
1. Materials challenges in nuclear energy10.1016/j.actamat.2012.11.004 ↗
2. Testing thermal gradient driving force for grain boundary migration using molecular dynamics simulations10.1016/j.actamat.2014.11.019 ↗
3. Radiation damage tolerant nanomaterials10.1016/j.mattod.2013.10.019 ↗
4. Efficient annealing of radiation damage near grain boundaries via interstitial emission10.1126/science.1183723 ↗
5. Towards an integrated materials characterization toolbox10.1557/jmr.2011.41 ↗
6. Effect of helium irradiation on Ti3AlC2 at 500 °C10.1016/j.scriptamat.2013.12.010 ↗
7. Defect microstructure in heavy-ion-bombarded (0001) ZnO10.1016/j.actamat.2012.07.046 ↗
8. In-situ luminescence monitoring of ion-induced damage evolution in SiO2 and Al2O310.1016/j.jlumin.2015.12.016 ↗
9. Investigation of thermal transport in composites and ion beam irradiated materials for nuclear energy applications10.1557/jmr.2016.421 ↗
10. Thermally activated point defect migration in copper10.1103/PhysRev.120.411 ↗
11. The resistivity recovery of high-purity and carbon doped iron following low-temperature electron-irradiation10.1080/00337578308207398 ↗
12. Real-time thermomechanical property monitoring during ion beam irradiation using in situ transient grating spectroscopy10.1016/j.nimb.2018.10.025 ↗
13. Interfacial thermal resistance in nanocrystalline yttria-stabilized zirconia10.1016/S1359-6454(02)00057-5 ↗
14. Low thermal conductivity oxides10.1557/mrs.2012.234 ↗
15. Understanding chemical expansion in non-stoichiometric oxides: ceria and zirconia case studies10.1002/adfm.201102648 ↗
16. Fundamental aspects of nuclear reactor fuel elements: prepared for the division of reactor development and demonstration, energy research and development administration, technical information center
17. Imaging grain microstructure in a model ceramic energy material with optically generated coherent acoustic phonons10.1038/s41467-020-15360-3 ↗
18. Kinetically evolving irradiation-induced point defect clusters in UO2 by molecular dynamics simulation10.1103/PhysRevB.80.104107 ↗
19. Multiscale simulation of xenon diffusion and grain boundary segregation in UO210.1016/j.jnucmat.2015.03.019 ↗
20. Linking atomic and mesoscopic scales for the modelling of the transport properties of uranium dioxide under irradiation10.1016/j.jnucmat.2015.02.026 ↗
21. Early stages of irradiation induced dislocations in urania10.1063/1.4967191 ↗
22. Development of a multiscale thermal conductivity model for fission gas in UO210.1016/j.jnucmat.2015.11.042 ↗
23. In-situ measurement of irradiation behavior in LiNbO310.1016/j.nimb.2020.03.007 ↗
24. The high burn-up structure in nuclear fuel10.1016/S1369-7021(10)70221-2 ↗
25. Bubble formation and Kr distribution in Kr-irradiated UO210.1016/j.jnucmat.2014.09.026 ↗
26. In-situ TEM observation of nano-void formation in UO2 under irradiation10.1016/j.nimb.2013.10.055 ↗
27. In Situ TEM observation of dislocation evolution in polycrystalline UO210.1007/s11837-014-1186-6 ↗
28. Ingrowth of lattice-defects in alpha irradiated UO2 single-crystals10.1016/0022-3115(81)90400-1 ↗
29. Irradiation induced lattice-defects in UO210.1016/0022-3115(78)90430-0 ↗
30. Thermal recovery of lattice defects in Alpha-irradiated UO2 crystals10.1016/0022-3115(83)90259-3 ↗
31. Thermal recovery of defects in neutron-irradiated UO210.1016/0022-3115(79)90194-6 ↗
32. Thermal evolution of the vacancy defects distribution in 1 MeV helium implanted sintered UO210.1016/j.nimb.2007.04.059 ↗
33. Evolution of extended defects in polycrystalline UO2 under heavy ion irradiation: combined TEM, XRD and Raman study10.1016/j.nimb.2015.08.091 ↗
34. Lattice strain in irradiated materials unveils a prevalent defect evolution mechanism
35. Atomistic modeling of intrinsic and radiation-enhanced fission gas (Xe) diffusion in UO2 +/- x: implications for nuclear fuel performance modeling10.1016/j.jnucmat.2014.03.041 ↗
36. First-principles calculation and experimental study of oxygen diffusion in uranium dioxide10.1103/PhysRevB.83.035126 ↗
37. Influence of charge states on energies of point defects and clusters in uranium dioxide10.1103/PhysRevB.85.144101 ↗
38. Energetics of intrinsic point defects in uranium dioxide from electronic-structure calculations10.1016/j.jnucmat.2008.10.003 ↗
39. Calculation of threshold displacement energies in UO210.1016/j.jnucmat.2019.04.002 ↗
40. Primary radiation damage on displacement cascades in UO2, ThO2 and (U0.5Th0.5)O-210.1016/j.commatsci.2018.08.024 ↗
41. Effect of the cascade energy on defect production in uranium dioxide10.1016/j.nimb.2010.12.075 ↗
42. Off-stoichiometric defect clustering in irradiated oxides10.1016/j.chemphys.2017.01.014 ↗
43. Quantification of irradiation-induced defects in UO2 using Raman and positron annihilation spectroscopies10.1016/j.actamat.2018.10.044 ↗
44. Possible Bose-condensate behavior in a quantum phase originating in a collective excitation in the chemically and optically doped Mott-Hubbard system UO2+x10.1103/PhysRevB.88.115135 ↗
45. Defect-induced Raman-spectra in doped CeO210.1103/PhysRevB.50.13297 ↗
46. 2.6 MeV proton irradiation effects on the surface integrity of depleted UO210.1016/j.nimb.2013.11.014 ↗
47. Microstructure changes and thermal conductivity reduction in UO2 following 3.9 MeV He2+ ion irradiation10.1016/j.jnucmat.2014.07.053 ↗
48. Thermal conductivity of UO2+x and U4O9-y10.1016/j.jnucmat.2013.07.063 ↗
49. On the use of SRIM for computing radiation damage exposure10.1016/j.nimb.2013.05.008 ↗
50. Impact of auto-irradiation on the thermophysical properties of oxide nuclear reactor fuels10.1016/j.jnucmat.2009.11.024 ↗
51. Characterization of ultralow thermal conductivity in anisotropic pyrolytic carbon coating for thermal management applications10.1016/j.carbon.2017.12.041 ↗
52. Local measurement of thermal conductivity and diffusivity10.1063/1.4936213 ↗
53. Impact of irradiation induced dislocation loops on thermal conductivity in ceramics10.1111/jace.16616 ↗
54. Thermal transport across nanoscale damage profile in sapphire irradiated by swift heavy ions10.1063/1.5126413 ↗
55. Orders of magnitude reduction in the thermal conductivity of polycrystalline diamond through carbon, nitrogen, and oxygen ion implantation10.1016/j.carbon.2019.09.076 ↗
56. Effect of ion irradiation on the thermal conductivity of UO2 and U3O8 epitaxial layers10.1016/j.jnucmat.2013.07.021 ↗
57. Adkins · 2020
58. Implementation of a multilayer model for measurement of thermal conductivity in ion beam irradiated samples using a modulated thermoreflectance approach10.1016/j.jnucmat.2018.06.013 ↗
59. Predicting damage production in monoatomic and multi-elemental targets using stopping and range of ions in matter code: challenges and recommendations10.1016/j.cossms.2019.06.001 ↗
60. On the Relation between Lattice-parameter and O/M Ratio for Uranium-dioxide Trivalent Rare-earth-oxide solid-solution10.1016/0022-3115(81)90544-4 ↗
61. Lattice constant in nonstoichiometric uranium dioxide from first principles
62. Revised effective ionic-radii and systematics studies of interatomic distances in halides and chalcogenides10.1107/S0567739476001551 ↗
63. Molecular dynamics simulation of thermal transport in UO2 containing uranium, oxygen, and fission-product defects10.1103/PhysRevApplied.6.044015 ↗
64. Phonon scattering by oxygen vacancies in ceramics10.1016/S0921-4526(98)01202-2 ↗
65. Phonon lifetime investigation of anharmonicity and thermal conductivity of UO2 by neutron scattering and theory10.1103/PhysRevLett.110.157401 ↗
66. Atomistic and experimental study on thermal conductivity of bulk and porous cerium dioxide10.1038/s41598-019-42807-5 ↗
67. Die Konstitution der Mischkristalle und die Raumfüllung der Atome10.1007/BF01349680 ↗
68. Thermal conductivity and lattice vibration modes
69. Defect production in ceramics10.1016/S0022-3115(97)00224-9 ↗
70. Lynds · 1963 · 58
71. Point defects and clustering in uranium dioxide by LSDA+U calculations10.1103/PhysRevB.77.104120 ↗
72. Thermal transport study in actinide oxides with point defects10.1016/j.net.2019.03.011 ↗
73. Thermal recovery mechanisms of UO2 lattices by defect annihilation10.1016/j.jallcom.2017.07.100 ↗
74. First-principles calculations of uranium diffusion in uranium dioxide10.1103/PhysRevB.86.035110 ↗
75. High-energy radiation damage in zirconia: modeling results10.1063/1.4866989 ↗
76. Electron energy-dependent formation of dislocation loops in CeO(2)10.1016/j.nimb.2008.03.204 ↗