Calculation of the Effective Delayed Neutron Fraction by Deterministic and Monte Carlo Methods

The studies on Accelerator-Driven Systems (ADSs) have renewed the interest in the theoretical and computational evaluation of the main integral parameters characterizing subcritical systems (e.g., reactivity, effective delayed neutron fraction βeff, and mean prompt neutron generation time). In parti...

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Main Authors: M. Carta, S. Dulla, V. Peluso, P. Ravetto, G. Bianchini
Format: Article
Language:English
Published: Wiley 2011-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2011/584256
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author M. Carta
S. Dulla
V. Peluso
P. Ravetto
G. Bianchini
author_facet M. Carta
S. Dulla
V. Peluso
P. Ravetto
G. Bianchini
author_sort M. Carta
collection DOAJ
description The studies on Accelerator-Driven Systems (ADSs) have renewed the interest in the theoretical and computational evaluation of the main integral parameters characterizing subcritical systems (e.g., reactivity, effective delayed neutron fraction βeff, and mean prompt neutron generation time). In particular, some kinetic parameters, as the effective delayed neutron fraction, are evaluated in Monte Carlo codes by formulations which do not require the calculation of the adjoint flux. This paper is focused on a theoretical and computational analysis about how the different βeff definitions are connected and which are the approximations inherent to the Monte Carlo definition with respect to the standard definition involving weighted integrals. By means of a refined transport computational analysis carried out in a coherent and consistent way, that is, using the same deterministic code and neutron data library for the βeff evaluation in different ways, the theoretical analysis is numerically confirmed. Both theoretical and numerical results confirm the effectiveness of the Monte Carlo βeff evaluation, at least in cases where spectral differences between total and prompt fluxes are negligible with respect to the value of the functionals entering the classical βeff formulation.
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spelling doaj-art-5bbd7d1a42284c14b1bf4ee7bcfb8d1f2025-02-03T05:50:22ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832011-01-01201110.1155/2011/584256584256Calculation of the Effective Delayed Neutron Fraction by Deterministic and Monte Carlo MethodsM. Carta0S. Dulla1V. Peluso2P. Ravetto3G. Bianchini4ENEA, C.R. Casaccia, Via Anguillarese 301, 00123 Roma, ItalyDipartimento di Energetica, Politecnico di Torino, Corso Duca degli Abruzzi 24, 10129 Torino, ItalyENEA, C.R.E. E. Clementel, Via Martiri di Monte Sole 4, 40129 Bologna, ItalyDipartimento di Energetica, Politecnico di Torino, Corso Duca degli Abruzzi 24, 10129 Torino, ItalyENEA, C.R. Casaccia, Via Anguillarese 301, 00123 Roma, ItalyThe studies on Accelerator-Driven Systems (ADSs) have renewed the interest in the theoretical and computational evaluation of the main integral parameters characterizing subcritical systems (e.g., reactivity, effective delayed neutron fraction βeff, and mean prompt neutron generation time). In particular, some kinetic parameters, as the effective delayed neutron fraction, are evaluated in Monte Carlo codes by formulations which do not require the calculation of the adjoint flux. This paper is focused on a theoretical and computational analysis about how the different βeff definitions are connected and which are the approximations inherent to the Monte Carlo definition with respect to the standard definition involving weighted integrals. By means of a refined transport computational analysis carried out in a coherent and consistent way, that is, using the same deterministic code and neutron data library for the βeff evaluation in different ways, the theoretical analysis is numerically confirmed. Both theoretical and numerical results confirm the effectiveness of the Monte Carlo βeff evaluation, at least in cases where spectral differences between total and prompt fluxes are negligible with respect to the value of the functionals entering the classical βeff formulation.http://dx.doi.org/10.1155/2011/584256
spellingShingle M. Carta
S. Dulla
V. Peluso
P. Ravetto
G. Bianchini
Calculation of the Effective Delayed Neutron Fraction by Deterministic and Monte Carlo Methods
Science and Technology of Nuclear Installations
title Calculation of the Effective Delayed Neutron Fraction by Deterministic and Monte Carlo Methods
title_full Calculation of the Effective Delayed Neutron Fraction by Deterministic and Monte Carlo Methods
title_fullStr Calculation of the Effective Delayed Neutron Fraction by Deterministic and Monte Carlo Methods
title_full_unstemmed Calculation of the Effective Delayed Neutron Fraction by Deterministic and Monte Carlo Methods
title_short Calculation of the Effective Delayed Neutron Fraction by Deterministic and Monte Carlo Methods
title_sort calculation of the effective delayed neutron fraction by deterministic and monte carlo methods
url http://dx.doi.org/10.1155/2011/584256
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