Study of a Low-power, Fast-neutron-based ADS
| Autor: | P. Figuera, Alessandro U. Rebora, Paolo Finocchiaro, Sandra Dulla, R. Cremonesi, Davide Chiesa, Marco Reale, M. Maggiore, Massimiliano Clemenza, M. Osipenko, Antonio Cammi, M. Schillacii, Sara Bortot, Piero Ravetto, A. Di Pietro, N. Colonnae, Paolo Saracco, Juan Esposito, M. Cagnazzo, Daniele Alloni, Maurizio Bruzzone, G. Cosentino, Massimo Barbagallo, Carlo Maria Viberti, Ezio Previtali, G. Preteh, Michele Prata, Luciano Calabretta, Giovanni Magrotti, P. Boccaccio, Fabio Panza, A. Kostyukov, M. Ricottik, L. Mansani, A. Borio di Tigliole, S. Manera, Domenico Santonocito, R. Alba, S. Monti, Augusto Lombardi, Andrea Salvini, G. Ricco, Marco Ciotti, O. Frasciellog, C. Maiolino, S. Frambati, Stefano Lorenzi, L. Piazza, Monica Sisti, M. Ripani, A. Celentano, A. Del Zoppo |
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| Rok vydání: | 2014 |
| Předmět: |
Neutrons
Nuclear transmutation Nuclear engineering Cyclotron chemistry.chemical_element Thermal power station Physics and Astronomy(all) Accelerator Driven Systems Transmutation 7. Clean energy Coolant law.invention Nuclear physics Fast nuclear reactors chemistry Conceptual design law Environmental science Neutron Radioactive waste Beryllium Decay heat Accelerators |
| Zdroj: | Physics Procedia. 60:54-60 |
| ISSN: | 1875-3892 |
| Popis: | Within European Partitioning & Transmutation research programs, infrastructures specifically dedicated to the study of funda- mental reactor physics and engineering parameters of future fast-neutron-based reactors are very important, being some of these features not available in present zero-power prototypes. This presentation will illustrate the conceptual design of an ADS with high safety standards, but ample flexibility for measurements. The design assumes as base option the 70 MeV, 0.75 mA proton cyclotron facility planned to be constructed at the INFN National Laboratory in Legnaro, Italy and a Beryllium target, with Helium gas as core coolant. Safety is guaranteed by limiting the thermal power to 200 kW, with a neutron multiplication coefficient around 0.94, loading the core with fuel containing Uranium enriched at 20% and a solid-lead diffuser. The small decay heat can be passively removed by thermal radiation from the vessel. Such a system could be used to study, among others, some specific aspects of neutron diffusion in lead, beam-core coupling, target cooling and could serve as a training facility. |
| Databáze: | OpenAIRE |
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