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Descripción
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| In this paper, we assess the capability of codes to predict fuel cycle parameters for conceptual transmutation designs. The sensitivity/uncertainty and the Monte Carlo methodologies implemented in ACAB code will be described and the applicability to different nuclear fields is presented. We have studied the impact of activation cross-section uncertainties on relevant fuel cycle parameters, and the nuclear data requirements are evaluated so that such parameters can meet the assigned design target accuracies. We conclude with recommendations for future nuclear data measurement programs, beyond the specific results obtained with the present nuclear data files and the limited available covariance information. | |
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Internacional
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Si |
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Nombre congreso
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IAEA TM on Specific Applications of Research Reactors: Provision of Nuclear Data |
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Tipo de participación
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960 |
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Lugar del congreso
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Viena (Austria) |
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Revisores
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Si |
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ISBN o ISSN
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DOI
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Fecha inicio congreso
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12/10/2009 |
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Fecha fin congreso
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16/10/2009 |
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Desde la página
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0 |
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Hasta la página
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0 |
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Título de las actas
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IAEA-NDC Report |