2021
DOI: 10.1016/j.jallcom.2021.159751
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Rate theory and experimental study of the irradiation induced defects in molybdenum alloy

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Cited by 4 publications
(2 citation statements)
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“…However, when Kr 2+ ion irradiates 10-18Cr (at.%) FeCrAl alloy in situ at a slightly higher temperature of 320 • C, the dislocation loop density increased with dose, but reached saturation at 2.5 dpa [7]. The higher irradiation temperature makes the dislocation loop density saturated at a lower dose, which is consistent with the previous simulation results of loop density in Mo [28]. Therefore, the dislocation loop density is expected to reach saturation before 2.5 dpa at the higher irradiation temperature of 330 • C compared to [7].…”
Section: Size and Density Of Dislocation Loopsupporting
confidence: 90%
“…However, when Kr 2+ ion irradiates 10-18Cr (at.%) FeCrAl alloy in situ at a slightly higher temperature of 320 • C, the dislocation loop density increased with dose, but reached saturation at 2.5 dpa [7]. The higher irradiation temperature makes the dislocation loop density saturated at a lower dose, which is consistent with the previous simulation results of loop density in Mo [28]. Therefore, the dislocation loop density is expected to reach saturation before 2.5 dpa at the higher irradiation temperature of 330 • C compared to [7].…”
Section: Size and Density Of Dislocation Loopsupporting
confidence: 90%
“…Here, we propose a possible solution to the mentioned issues that could be represented by compact and defect-free high melting point oxide strengthened metallic matrix configurations, integrating highly impermeable materials (e.g., oxides and metals) applicable as hydrogen permeation barriers (HPB). It was previously reported that oxide addition to a metallic matrix could influence the recrystallization behavior [9], while brittleness phenomena could be mitigated by particle dispersion strengthening [10][11][12]. Generally, these oxide-metal structures have been successfully integrated into a wide variety of industrial applications [13][14][15][16][17], and in the last decade, their applicability in the fusion power sector gained more interest while being promoted as high-strength nuclear materials with high resistance to brittleness and permeation [18][19][20][21][22][23][24][25][26][27].…”
Section: Introductionmentioning
confidence: 99%