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Descripción
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| Irradiation of Zirconium is studied using kinetic Monte Carlo model under fission reactor conditions. The initial cascade damage produced by 25 keV recoils at 600K is used in the calculations. The evolution of the microstructure has been followed for a number of dpa up to 0.5. In particular, the influence of self-interstitial cluster migration on the total defect concentration and size is analyzed. Results are compared with experimental data. | |
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Internacional
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No |
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JCR del ISI
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No |
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Título de la revista
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Journal of Nuclear Materials |
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ISSN
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0022-3115 |
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Factor de impacto JCR
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0 |
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Información de impacto
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Volumen
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362 |
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DOI
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Número de revista
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0 |
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Desde la página
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293 |
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Hasta la página
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299 |
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Mes
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SIN MES |
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Ranking
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