Cross section data in the resolved and unresolved resonance region are represented by nuclear reaction formalisms using parameters which are determined by fitting them to experimental data. Therefore, the quality of evaluated cross sections in the resonance region strongly depends on the experimental data used in the adjustment process and an assessment of the experimental covariance data is of primary importance in determining the accuracy of evaluated cross section data. In this contribution, uncertainty components of experimental observables resulting from total and reaction cross section experiments are quantified by identifying the metrological parameters involved in the measurement, data reduction and analysis process. In addition, different methods that can be applied to propagate the covariance of the experimental observables (i.e. transmission and reaction yields) to the covariance of the resonance parameters are discussed and compared. The methods being discussed are: conventional uncertainty propagation, Monte Carlo sampling and marginalization. It is demonstrated that the final covariance matrix of the resonance parameters not only strongly depends on the type of experimental observables used in the adjustment process, the experimental conditions and the characteristics of the resonance structure, but also on the method that is used to propagate the covariances. Finally, a special data reduction concept and format is presented, which offers the possibility to store the full covariance information of experimental data in the EXFOR library and provides the information required to perform a full covariance evaluation.

Determination of Resonance Parameters and their Covariances from Neutron Induced Reaction Cross Section Data / P. Schillebeeckx; B. Becker; Y. Danon; K. Guber; H. Harada; J. Heyse; A.R. Junghans; S. Kopecky; C. Massimi; M.C. Moxon; N. Otuka; I. Sirakov; K. Volev. - In: NUCLEAR DATA SHEETS. - ISSN 0090-3752. - STAMPA. - 113:(2012), pp. 3054-3100. [10.1016/j.nds.2012.11.005]

Determination of Resonance Parameters and their Covariances from Neutron Induced Reaction Cross Section Data

MASSIMI, CRISTIAN;
2012

Abstract

Cross section data in the resolved and unresolved resonance region are represented by nuclear reaction formalisms using parameters which are determined by fitting them to experimental data. Therefore, the quality of evaluated cross sections in the resonance region strongly depends on the experimental data used in the adjustment process and an assessment of the experimental covariance data is of primary importance in determining the accuracy of evaluated cross section data. In this contribution, uncertainty components of experimental observables resulting from total and reaction cross section experiments are quantified by identifying the metrological parameters involved in the measurement, data reduction and analysis process. In addition, different methods that can be applied to propagate the covariance of the experimental observables (i.e. transmission and reaction yields) to the covariance of the resonance parameters are discussed and compared. The methods being discussed are: conventional uncertainty propagation, Monte Carlo sampling and marginalization. It is demonstrated that the final covariance matrix of the resonance parameters not only strongly depends on the type of experimental observables used in the adjustment process, the experimental conditions and the characteristics of the resonance structure, but also on the method that is used to propagate the covariances. Finally, a special data reduction concept and format is presented, which offers the possibility to store the full covariance information of experimental data in the EXFOR library and provides the information required to perform a full covariance evaluation.
2012
Determination of Resonance Parameters and their Covariances from Neutron Induced Reaction Cross Section Data / P. Schillebeeckx; B. Becker; Y. Danon; K. Guber; H. Harada; J. Heyse; A.R. Junghans; S. Kopecky; C. Massimi; M.C. Moxon; N. Otuka; I. Sirakov; K. Volev. - In: NUCLEAR DATA SHEETS. - ISSN 0090-3752. - STAMPA. - 113:(2012), pp. 3054-3100. [10.1016/j.nds.2012.11.005]
P. Schillebeeckx; B. Becker; Y. Danon; K. Guber; H. Harada; J. Heyse; A.R. Junghans; S. Kopecky; C. Massimi; M.C. Moxon; N. Otuka; I. Sirakov; K. Volev
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11585/132895
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