| Autor: |
Ripani Marco, Frambati Stefano, Mansani Luigi, Bruzzone Maurizio, Reale Marco, Monti Stefano, Ciotti Marco, Barbagallo Massimo, Colonna Nicola, Celentano Andrea, Osipenko Mikhail, Ricco Giovanni, Saracco Paolo, Viberti Carlo Maria, Frasciello Oscar, Boccaccio Pasquale, Esposito Juan, Lombardi Augusto, Maggiore Mario, Piazza Leandro A. C., Prete Gianfranco, Alba Rosa, Calabretta Luciano, Cosentino Gianluigi, Del Zoppo Antonio, Di Pietro Alessia, Figuera Pierpaolo, Finocchiaro Paolo, Maiolino Cettina, Santonocito Domenico, Schillaci Maria, Chiesa Davide, Clemenza Massimiliano, Previtali Ezio, Sisti Monica, Kostyukov Alexander, Cammi Antonio, Bortot Sara, Lorenzi Stefano, Ricotti Marco, Dulla Sandra, Ravetto Piero, Lomonaco Guglielmo, Rebora Alessandro, Alloni Daniele, di Tigliole Andrea Borio, Cagnazzo Marcella, Cremonesi Riccardo, Magrotti Giovanni, Manera Sergio, Panza Fabio, Prata Michele, Salvini Andrea |
| Jazyk: |
angličtina |
| Rok vydání: |
2014 |
| Předmět: |
|
| Zdroj: |
EPJ Web of Conferences, Vol 79, p 02004 (2014) |
| Druh dokumentu: |
article |
| ISSN: |
2100-014X |
| DOI: |
10.1051/epjconf/20137902004 |
| Popis: |
Within European Partitioning & Transmutation research programs, infrastructures specifically dedicated to the study of fundamental 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 Accelerator-Driven System with high safety standards, but ample flexibility for measurements. The design assumes as base option a 70 MeV, 0.75 mA proton cyclotron, as the one which will be installed 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% inserted in 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: |
Directory of Open Access Journals |
| Externí odkaz: |
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