RAVEN (Reactor Analysis and Virtual control Environment) is a software code under development at Idaho National Laboratory aimed at performing probabilistic risk assessment and uncertainty quantification using RELAP-7, for which it acts also as a simulation controller. In this paper we will present the equations characterizing a dynamic stochastic system and we will then discuss the behavior of each stochastic term and how it is accounted for in the RAVEN software design. Moreover we will present preliminary results of the implementation

Mathematical Framework for the Analysis of Dynamic Stochastic Systems with the RAVEN code / C., Rabiti; Alfonsi, Andrea; D., Mandelli; J., Cogliati; R., Kinoshita. - 1:(2013), pp. ...-.... (Intervento presentato al convegno International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2013 tenutosi a Sun Valley; United States nel 5-9 Maggio 2013).

Mathematical Framework for the Analysis of Dynamic Stochastic Systems with the RAVEN code

ALFONSI, ANDREA;
2013

Abstract

RAVEN (Reactor Analysis and Virtual control Environment) is a software code under development at Idaho National Laboratory aimed at performing probabilistic risk assessment and uncertainty quantification using RELAP-7, for which it acts also as a simulation controller. In this paper we will present the equations characterizing a dynamic stochastic system and we will then discuss the behavior of each stochastic term and how it is accounted for in the RAVEN software design. Moreover we will present preliminary results of the implementation
2013
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2013
probabilistic risk assessment; dynamic stochastic systems; uncertainty quantification
04 Pubblicazione in atti di convegno::04b Atto di convegno in volume
Mathematical Framework for the Analysis of Dynamic Stochastic Systems with the RAVEN code / C., Rabiti; Alfonsi, Andrea; D., Mandelli; J., Cogliati; R., Kinoshita. - 1:(2013), pp. ...-.... (Intervento presentato al convegno International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2013 tenutosi a Sun Valley; United States nel 5-9 Maggio 2013).
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11573/541740
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