In this paper, we present a statistical method, based on Bayesian statistics, to evaluate the neutron flux spectrum from the activation data of different isotopes. The experimental data were acquired during a neutron activation analysis (NAA) experiment [1] performed at the TRIGA Mark II reactor of Pavia University (Italy). In order to evaluate the neutron flux spectrum, subdivided in energy groups, we must solve a system of linear equations containing the grouped cross sections and the activation rate data. We solve this problem with Bayesian statistical analysis, including the uncertainties of the coefficients and the a priori information about the neutron flux. A program for the analysis of Bayesian hierarchical models, based on Markov Chain Monte Carlo (MCMC) simulations, is used to define the problem statistical model and solve it. The energy group fluxes and their uncertainties are then determined with great accuracy and the correlations between the groups are analyzed. Finally, the dependence of the results on the prior distribution choice and on the group cross section data is investigated to confirm the reliability of the analysis.

Chiesa, D., Previtali, E., Sisti, M. (2014). Bayesian Statistical Analysis Applied to NAA Data for Neutron Flux Spectrum Determination. NUCLEAR DATA SHEETS, 118, 564-567 [10.1016/j.nds.2014.04.136].

Bayesian Statistical Analysis Applied to NAA Data for Neutron Flux Spectrum Determination

CHIESA, DAVIDE;Previtali, E;SISTI, MONICA
2014

Abstract

In this paper, we present a statistical method, based on Bayesian statistics, to evaluate the neutron flux spectrum from the activation data of different isotopes. The experimental data were acquired during a neutron activation analysis (NAA) experiment [1] performed at the TRIGA Mark II reactor of Pavia University (Italy). In order to evaluate the neutron flux spectrum, subdivided in energy groups, we must solve a system of linear equations containing the grouped cross sections and the activation rate data. We solve this problem with Bayesian statistical analysis, including the uncertainties of the coefficients and the a priori information about the neutron flux. A program for the analysis of Bayesian hierarchical models, based on Markov Chain Monte Carlo (MCMC) simulations, is used to define the problem statistical model and solve it. The energy group fluxes and their uncertainties are then determined with great accuracy and the correlations between the groups are analyzed. Finally, the dependence of the results on the prior distribution choice and on the group cross section data is investigated to confirm the reliability of the analysis.
Articolo in rivista - Articolo scientifico
Neutron flux spectrum Bayesian statistics Research reactors Data analysis
English
2014
118
564
567
none
Chiesa, D., Previtali, E., Sisti, M. (2014). Bayesian Statistical Analysis Applied to NAA Data for Neutron Flux Spectrum Determination. NUCLEAR DATA SHEETS, 118, 564-567 [10.1016/j.nds.2014.04.136].
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/10281/51955
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