Nuclear data requirements for the ADS conceptual design EFIT: Uncertainty and sensitivity study

García Herranz, Nuria; Cabellos de Francisco, Oscar Luis; Álvarez Velarde, F.; Sanz Gonzalo, Javier; González Romero, E.M. y Juan Ruiz, Jesús (2010). Nuclear data requirements for the ADS conceptual design EFIT: Uncertainty and sensitivity study. "Annals of Nuclear Energy", v. 37 ; pp. 1570-1579. ISSN 0306-4549. https://doi.org/10.1016/j.anucene.2010.06.00.

Descripción

Título: Nuclear data requirements for the ADS conceptual design EFIT: Uncertainty and sensitivity study
Autor/es:
  • García Herranz, Nuria
  • Cabellos de Francisco, Oscar Luis
  • Álvarez Velarde, F.
  • Sanz Gonzalo, Javier
  • González Romero, E.M.
  • Juan Ruiz, Jesús
Tipo de Documento: Artículo
Título de Revista/Publicación: Annals of Nuclear Energy
Fecha: Enero 2010
Volumen: 37
Materias:
Palabras Clave Informales: ADS; Cross-section uncertainties; Uncertainty propagation; Sensitivity technique; Monte Carlo simulation; Target accuracies
Escuela: E.T.S.I. Industriales (UPM)
Departamento: Ingeniería Nuclear [hasta 2014]
Licencias Creative Commons: Reconocimiento - Sin obra derivada - No comercial

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Resumen

In this paper, we assess the impact of activation cross-section uncertainties on relevant fuel cycle parameters for a conceptual design of a modular European Facility for Industrial Transmutation (EFIT) with a “double strata” fuel cycle. Next, the nuclear data requirements are evaluated so that the parameters can meet the assigned design target accuracies. Different discharge burn-up levels are considered: a low burn-up, corresponding to the equilibrium cycle, and a high burn-up level, simulating the effects on the fuel of the multi-recycling scenario. In order to perform this study, we propose a methodology in two steps. Firstly, we compute the uncertainties on the system parameters by using a Monte Carlo simulation, as it is considered the most reliable approach to address this problem. Secondly, the analysis of the results is performed by a sensitivity technique, in order to identify the relevant reaction channels and prioritize the data improvement needs. Cross-section uncertainties are taken from the EAF-2007/UN library since it includes data for all the actinides potentially present in the irradiated fuel. Relevant uncertainties in some of the fuel cycle parameters have been obtained, and 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. A comparison with the uncertainty and accuracy analysis recently published by the WPEC-Subgroup26 of the OECD using BOLNA covariance matrices is performed. Despite the differences in the transmuter reactor used for the analysis, some conclusions obtained by Subgroup26 are qualitatively corroborated, and improvements for additional cross sections are suggested.

Más información

ID de Registro: 6726
Identificador DC: http://oa.upm.es/6726/
Identificador OAI: oai:oa.upm.es:6726
Identificador DOI: 10.1016/j.anucene.2010.06.00
URL Oficial: http://www.sciencedirect.com/science/journal/03064549
Depositado por: Memoria Investigacion
Depositado el: 27 Abr 2011 08:34
Ultima Modificación: 20 Abr 2016 15:54
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