Increases in computational power and pressure for more accurate simulations and estimations of accident scenario consequences are driving the need for Dynamic Probabilistic Risk Assessment (PRA) [1] of very complex models. While more sophisticated algorithms and computational power address the back end of this challenge, the front end is still handled by engineers that need to extract meaningful information from the large amount of data and build these complex models. Compounding this problem is the difficulty in knowledge transfer and retention, and the increasing speed of software development. The above-described issues would have negatively impacted deployment of the new high fidelity plant simulator RELAP-7 (Reactor Excursion and Leak Analysis Program) at Idaho National Laboratory. Therefore, RAVEN that was initially focused to be the plant controller for RELAP-7 will help mitigate future RELAP-7 software engineering risks. In order to accomplish such a task Reactor Analysis and Vi

RAVEN: a GUI and an Artificial Intelligence Engine in a Dynamic PRA Framework / C., Rabiti; Alfonsi, Andrea; D., Mandelli; J., Cogliati; R., Kinoshita. - STAMPA. - 108:(2013), pp. 533-536. (Intervento presentato al convegno American Nuclear Society 2013 Annual Meeting "Next Generation Nuclear Energy: Prospects and Challenges" tenutosi a Atlanta, GA; United States).

RAVEN: a GUI and an Artificial Intelligence Engine in a Dynamic PRA Framework

ALFONSI, ANDREA;
2013

Abstract

Increases in computational power and pressure for more accurate simulations and estimations of accident scenario consequences are driving the need for Dynamic Probabilistic Risk Assessment (PRA) [1] of very complex models. While more sophisticated algorithms and computational power address the back end of this challenge, the front end is still handled by engineers that need to extract meaningful information from the large amount of data and build these complex models. Compounding this problem is the difficulty in knowledge transfer and retention, and the increasing speed of software development. The above-described issues would have negatively impacted deployment of the new high fidelity plant simulator RELAP-7 (Reactor Excursion and Leak Analysis Program) at Idaho National Laboratory. Therefore, RAVEN that was initially focused to be the plant controller for RELAP-7 will help mitigate future RELAP-7 software engineering risks. In order to accomplish such a task Reactor Analysis and Vi
2013
American Nuclear Society 2013 Annual Meeting "Next Generation Nuclear Energy: Prospects and Challenges"
Reactor Simulation; Probabilistic Risk Assment; uncertainty quantification; MONTE-CARLO SIMULATION
04 Pubblicazione in atti di convegno::04b Atto di convegno in volume
RAVEN: a GUI and an Artificial Intelligence Engine in a Dynamic PRA Framework / C., Rabiti; Alfonsi, Andrea; D., Mandelli; J., Cogliati; R., Kinoshita. - STAMPA. - 108:(2013), pp. 533-536. (Intervento presentato al convegno American Nuclear Society 2013 Annual Meeting "Next Generation Nuclear Energy: Prospects and Challenges" tenutosi a Atlanta, GA; United States).
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11573/541748
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