Published November 2010 | Version v1
Journal article

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

  • 1. Instituto de Fusion Nuclear, Universidad Politecnica de Madrid (Spain)
  • 2. Departamento de Ingenieria Nuclear, Universidad Politecnica de Madrid (Spain)
  • 3. CIEMAT (Spain)
  • 4. Departamento de Ingenieria Energetica, UNED (Spain)
  • 5. Laboratorio de Estadistica, Universidad Politecnica de Madrid (Spain)

Description

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.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.anucene.2010.06.006

Additional details

Identifiers

DOI
10.1016/j.anucene.2010.06.006;
PII
S0306-4549(10)00208-2;

Publishing Information

Journal Title
Annals of Nuclear Energy (Oxford)
Journal Volume
37
Journal Issue
11
Journal Page Range
p. 1570-1579
ISSN
0306-4549
CODEN
ANENDJ

Optional Information

Copyright
Copyright (c) 2010 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.