2022
DOI: 10.1016/j.jnucmat.2021.153377
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Recent trends in metallic fast reactor fuels research

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Cited by 17 publications
(8 citation statements)
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“…In the last years, over 10,000 U-10Zr fuel pins have been irradiated in the test reactors and new advanced Post-Irradiation Examination (PIE) data has been collected at Idaho National Laboratory (INL). The data includes observations on fuel swelling, Zr redistribution, FCCI, and FCMI phenomena, obtained through various characterization techniques such as neutron radiography, pin profilometry, gamma scan, fission gas release analysis, metallography, micro-hardness, isotopic chemical analysis, and high-resolution/micro-nano scale characterization [8][9][10][11][12][13][14][15][16][17]. New advanced characterization techniques employ multi-source data, including Scanning Electron Microscopy (SEM) images, Energy-Dispersive Spectroscopy (EDS) images, and Scanning Transmission Electron Microscopy (STEM), which provide qualitative material information from the optical scale, overall microstructure and pore distribution from SEM and EDS microscale, and phase/crystal structure identification from STEM nanoscale.…”
Section: Introductionmentioning
confidence: 99%
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“…In the last years, over 10,000 U-10Zr fuel pins have been irradiated in the test reactors and new advanced Post-Irradiation Examination (PIE) data has been collected at Idaho National Laboratory (INL). The data includes observations on fuel swelling, Zr redistribution, FCCI, and FCMI phenomena, obtained through various characterization techniques such as neutron radiography, pin profilometry, gamma scan, fission gas release analysis, metallography, micro-hardness, isotopic chemical analysis, and high-resolution/micro-nano scale characterization [8][9][10][11][12][13][14][15][16][17]. New advanced characterization techniques employ multi-source data, including Scanning Electron Microscopy (SEM) images, Energy-Dispersive Spectroscopy (EDS) images, and Scanning Transmission Electron Microscopy (STEM), which provide qualitative material information from the optical scale, overall microstructure and pore distribution from SEM and EDS microscale, and phase/crystal structure identification from STEM nanoscale.…”
Section: Introductionmentioning
confidence: 99%
“…Advanced PIE technologies have enabled researchers to gain qualitative understanding of the irradiation behavior of U-10Zr fuel, including Zr redistribution, FCMI, and FCCI [8][9][10][11][12][13][14][15][16][17]. For example, Salvato et al [12] investigated the Zr redistribution on a U-10Zr fuel cross-section, named FA, that was irradiated to a burnup of approximately 13.2at.%.…”
Section: Introductionmentioning
confidence: 99%
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“…6,7 A lot of new PIE data within the sub-nanometer to micrometer scale has been recently generated. [8][9][10] Two main challenges of this fuel material are zirconium redistribution (Fuel Constituent Migration), 11 and fuel-cladding chemical interactions (FCCI). 12 FCCI is a chemical reaction between nuclear fuel and cladding (a thin-walled metal as first barrier for retention of fission products), which creates an important challenge to overcome in metallic fuels.…”
Section: Introductionmentioning
confidence: 99%
“…7,10 It is essential to achieve a comprehensive understanding of the zirconium redistribution (phase distribution) in order to better predict fuel performance. 11 A U-10Zr fuel cross-section would host Zr redistribution in three major phases: 𝛾 phase (a continuous body centered cubic solid solution between U and Zr), noted as the (U, Zr) matrix; 𝛼 -U matrix; and 𝛼 -U + UZr2. The Zr redistributes across the pin radius and forms up to three distinctive zones by different U/Zr contents.…”
Section: Introductionmentioning
confidence: 99%