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Descripción
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| The aim of this work is to review different Monte Carlo techniques used to propagate nuclear data uncertainties. Firstly, we introduced Monte Carlo technique applied for Uncertainty Quantification studies in safety calculations of large scale systems. As an example, the impact of nuclear data uncertainty of JEFF-3.3 235U, 238U and 239Pu is demonstrated for the main design parameters of a typical 3-loop PWR Westinghouse unit. Secondly, the Bayesian Monte Carlo technique for data adjustment is presented. An example for 235U adjustment using criticality and shielding integral benchmarks shows the importance of performing joint adjustment based on different set of integral benchmar | |
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Internacional
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Si |
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Nombre congreso
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5th International Workshop on Nuclear Data Evaluation for Reactor Applications. |
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Tipo de participación
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960 |
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Lugar del congreso
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Aix-en-Provence, Francia |
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Revisores
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Si |
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ISBN o ISSN
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978-2-7598-1970-6 |
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DOI
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Fecha inicio congreso
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08/10/2018 |
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Fecha fin congreso
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12/10/2018 |
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Desde la página
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8 |
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Hasta la página
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14 |
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Título de las actas
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Book of Abastracts |