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2 results on '"Artioli, C."'

1. The core design of ALFRED, a demonstrator for the European lead-cooled reactors.

Author

Grasso, G., Petrovich, C., Mattioli, D., Artioli, C., Sciora, P., Gugiu, D., Bandini, G., Bubelis, E., and Mikityuk, K.

Subjects
*NUCLEAR reactor cores, *PARAMETER estimation, *NUCLEAR reactor safety measures, *CODING theory, *TRANSIENT analysis, *TEMPERATURE effect
Abstract

The European Union has recently co-funded the LEADER (Lead-cooled European Advanced DEmonstration Reactor) project, in the frame of which the preliminary designs of an industrial size lead-cooled reactor (1500 MW th ) and of its demonstrator reactor (300 MW th ) were developed. The latter is called ALFRED (Advanced Lead-cooled Fast Reactor European Demonstrator) and its core, as designed and characterized in the project, is presented here. The core parameters have been fixed in a comprehensive approach taking into account the main technological constraints and goals of the system from the very beginning: the limiting temperature of the clad and of the fuel, the Pu enrichment, the achievement of a burn-up of 100 GWd/t, the respect of the integrity of the system even in design extension conditions (DEC). After the general core design has been fixed, it has been characterized from the neutronic point of view by two independent codes (MCNPX and ERANOS), whose results are compared. The power deposition and the reactivity coefficient calculations have been used respectively as input for the thermal-hydraulic analysis (TRACE, CFD and ANTEO codes) and for some preliminary transient calculations (RELAP, CATHARE and SIM-LFR codes). The results of the lead activation analysis are also presented (FISPACT code). Some issues of the core design are to be reviewed and improved, uncertainties are still to be evaluated, but the verifications performed so far confirm the promising safety features of the lead-cooled fast reactors. [ABSTRACT FROM AUTHOR]

Published
2014
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2. The core design of ALFRED, a demonstrator for the European lead-cooled reactors

Author

D. Gugiu, C. Petrovich, Giacomino Bandini, Konstantin Mikityuk, Evaldas Bubelis, P. Sciora, C. Artioli, Giacomo Grasso, Davide Mattioli, Artioli, C., Petrovich, C., Grasso, G., and Mattioli, D.

Subjects
Nuclear and High Energy Physics, Engineering, business.industry, Mechanical Engineering, Nuclear engineering, Power deposition, Frame (networking), Computational fluid dynamics, Core (optical fiber), Nuclear Energy and Engineering, Lead-cooled fast reactor, media_common.cataloged_instance, General Materials Science, Transient (oscillation), European union, Safety, Risk, Reliability and Quality, business, Waste Management and Disposal, Simulation, media_common, Eranos
Abstract

The European Union has recently co-funded the LEADER (Lead-cooled European Advanced DEmonstration Reactor) project, in the frame of which the preliminary designs of an industrial size lead-cooled reactor (1500 MW th ) and of its demonstrator reactor (300 MW th ) were developed. The latter is called ALFRED (Advanced Lead-cooled Fast Reactor European Demonstrator) and its core, as designed and characterized in the project, is presented here. The core parameters have been fixed in a comprehensive approach taking into account the main technological constraints and goals of the system from the very beginning: the limiting temperature of the clad and of the fuel, the Pu enrichment, the achievement of a burn-up of 100 GWd/t, the respect of the integrity of the system even in design extension conditions (DEC). After the general core design has been fixed, it has been characterized from the neutronic point of view by two independent codes (MCNPX and ERANOS), whose results are compared. The power deposition and the reactivity coefficient calculations have been used respectively as input for the thermal-hydraulic analysis (TRACE, CFD and ANTEO codes) and for some preliminary transient calculations (RELAP, CATHARE and SIM-LFR codes). The results of the lead activation analysis are also presented (FISPACT code). Some issues of the core design are to be reviewed and improved, uncertainties are still to be evaluated, but the verifications performed so far confirm the promising safety features of the lead-cooled fast reactors.

Published
2014

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