EPJ Web of Conferences (Jan 2014)

Study of an intrinsically safe infrastructure for training and research on nuclear technologies

  • 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

DOI
https://doi.org/10.1051/epjconf/20137902004
Journal volume & issue
Vol. 79
p. 02004

Abstract

Read online

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.