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Descripción
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| The assessment of the uncertainty levels on the design and safety parameters for the innovative European Sodium Fast Reactor (ESFR) is mandatory. Some of these relevant safety quantities are the Doppler and void reactivity coefficients, whose uncertainties are quantified. Besides, the nuclear reaction data where an improvement will certainly benefit the design accuracy are identified. This work has been performed with the SCALE 6.1 codes suite and its multigroups cross sections library based on ENDF/B-VII.0 evaluation. | |
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Internacional
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Si |
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JCR del ISI
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Si |
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Título de la revista
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Nuclear Data Sheets |
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ISSN
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0090-3752 |
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Factor de impacto JCR
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2,667 |
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Información de impacto
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Datos JCR del año 2012 |
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Volumen
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118 |
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DOI
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http://dx.doi.org/10.1016/j.nds.2014.04.127 |
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Número de revista
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Desde la página
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535 |
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Hasta la página
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537 |
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Mes
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SIN MES |
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Ranking
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