Descripción
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Fuel cycles are designed with the aim of obtaining the highest amount of energy possible. Since higher burnup values are reached, it is necessary to improve our disposal designs, traditionally based on the conservative assumption that they contain fresh fuel. The criticality calculations involved must consider burnup by making the most of the experimental and computational capabilities developed, respectively, to measure and predict the isotopic content of the spent nuclear fuel. These high burnup scenarios encourage a review of the computational tools to find out possible weaknesses in the nuclear data libraries, in the methodologies applied and their applicability range. Experimental measurements of the spent nuclear fuel provide the perfect framework to benchmark the most well-known and established codes, both in the industry and academic research activity. | |
Internacional
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Si |
JCR del ISI
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Si |
Título de la revista
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ANNALS OF NUCLEAR ENERGY |
ISSN
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0306-4549 |
Factor de impacto JCR
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0,905 |
Información de impacto
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Volumen
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57 |
DOI
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10.1016/j.anucene.2012.11.034 |
Número de revista
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Desde la página
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199 |
Hasta la página
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208 |
Mes
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SIN MES |
Ranking
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0 |