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

García Herranz, Nuria and Cabellos de Francisco, Oscar Luis and Álvarez Velarde, F. and Sanz Gonzalo, Javier and González Romero, E.M. and 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.

Description

Title: Nuclear data requirements for the ADS conceptual design EFIT: Uncertainty and sensitivity study
Author/s:
  • García Herranz, Nuria
  • Cabellos de Francisco, Oscar Luis
  • Álvarez Velarde, F.
  • Sanz Gonzalo, Javier
  • González Romero, E.M.
  • Juan Ruiz, Jesús
Item Type: Article
Título de Revista/Publicación: Annals of Nuclear Energy
Date: January 2010
ISSN: 0306-4549
Volume: 37
Subjects:
Freetext Keywords: ADS; Cross-section uncertainties; Uncertainty propagation; Sensitivity technique; Monte Carlo simulation; Target accuracies
Faculty: E.T.S.I. Industriales (UPM)
Department: Ingeniería Nuclear [hasta 2014]
Creative Commons Licenses: Recognition - No derivative works - Non commercial

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Abstract

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.

More information

Item ID: 6726
DC Identifier: http://oa.upm.es/6726/
OAI Identifier: oai:oa.upm.es:6726
DOI: 10.1016/j.anucene.2010.06.00
Official URL: http://www.sciencedirect.com/science/journal/03064549
Deposited by: Memoria Investigacion
Deposited on: 27 Apr 2011 08:34
Last Modified: 20 Apr 2016 15:54
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