Evolution of extended defects in polycrystalline Au-irradiated UO 2  using  in situ  TEM: Temperature and fluence effects

Onofri, C.; Sabathier, C.; Baumier, Cédric; Bachelet, C.; Palancher, H.; Legros, Marc

doi:10.1016/j.jnucmat.2016.10.011

Cited by 30 publications

(21 citation statements)

References 27 publications

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“…Another possibility is that loops undergo unfaulting and/or loop merging, which results in decrease in loop density and has been previously reported especially when materials are subject to higher irradiation doses [89][90]. Nevertheless, the error bars for loop density estimation prevent us from concluding if any of these mechanisms are active in current work.…”

Section: Defect Evolutionmentioning

confidence: 78%

Phase and defect evolution in uranium-nitrogen-oxygen system under irradiation

Khafizov

Jiang

et al. 2021

Acta Materialia

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Section: Defect Evolutionmentioning

confidence: 78%

Phase and defect evolution in uranium-nitrogen-oxygen system under irradiation

Khafizov

Jiang

et al. 2021

Acta Materialia

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“…The loop density increases with the irradiation fluence up to a saturation value, which depends on the temperature [22,23,25]. Then, a decrease occurs due to the formation of dislocation line.…”

Section: Discussionmentioning

confidence: 99%

“…Point defects generated by irradiation can cluster forming extended defects such as voids and dislocation loops. Several studies report the nucleation of dislocations loops at very low damage level [22][23][24][25][26]. For instance, Onofri et al have in situ observed the first dislocation loops nucleation under irradiation at -180°C with 0.39 MeV Xe ions from a damage level of around 0.008 dpa [25] (Fig.…”

Section: Discussionmentioning

confidence: 99%

Effect of ballistic damage in UO2 samples under ion beam irradiations studied by in situ Raman spectroscopy

Gutierrez

Onofri

Miro

et al. 2018

Nuclear Instruments and Methods in Physics Research Section B:

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The damage induced in uranium dioxide (UO 2) during ion irradiation at low energy was studied by micro-Raman spectroscopy. Polycrystalline UO 2 samples were irradiated by 0.9-MeV I, 2-MeV Au at 25°C and by 4-MeV Kr ions at-160°C in a wide range of fluence. In situ Raman measurements reveal similar spectra evolution no matter the ion beam used. The T 2g band centred at 445 cm-1 related to the fluorine structure reveals a broadening with the irradiation damage increase. In addition, several bands ranging from 500 to 700 cm-1 , which are attributed to sub-or sur-stoichiometric structural defects, are observed at the first time of irradiation. Their intensities rise up with the irradiation fluence increase to a similar asymptotic relative values for all the irradiation conditions. The obtained Raman kinetics are compared with data from the literature on the microstructure evolution observed by Transmission Electronic Microscopy (TEM) and on the fraction of displaced atoms determined by Rutherford Backscattering Spectroscopy in channelling mode (RBS-C).

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“…The primary focus here will be key findings tied to ion beam irradiation studies. Ion beam irradiation has proven a flexible tool for the generation of defects found in real fuel [29,304,305,306,307,308,309,310,311,312,313,314,315,316,317,318,319,320,321,322,323,324,325,326,327,328].…”

Section: Crystalline Defect Generation Evolution and Characterizationmentioning

confidence: 99%

Thermal Energy Transport in Oxide Nuclear Fuel

et al. 2021

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To efficiently capture the energy of the nuclear bond, advanced nuclear reactor concepts seek solid fuels that must withstand unprecedented temperature and radiation extremes. In these advanced fuels, thermal energy transport under irradiation is directly related to reactor performance as well as reactor safety. The science of thermal transport in nuclear fuel is a grand challenge due to both computational and experimental complexities. Here, we provide a comprehensive review of thermal transport research on two actinide oxides: one currently in use in commercial nuclear reactors, uranium dioxide (UO2), and one advanced fuel candidate material, thorium dioxide (ThO2). In both materials, 5Concluding Remarks .

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Evolution of extended defects in polycrystalline Au-irradiated UO 2 using in situ TEM: Temperature and fluence effects

Cited by 30 publications

References 27 publications

Phase and defect evolution in uranium-nitrogen-oxygen system under irradiation

Phase and defect evolution in uranium-nitrogen-oxygen system under irradiation

Effect of ballistic damage in UO2 samples under ion beam irradiations studied by in situ Raman spectroscopy

Thermal Energy Transport in Oxide Nuclear Fuel

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