EPJ Web of Conferences
Volume 79, 2014E2C 2013 – 3rd European Energy Conference
|Number of page(s)||9|
|Section||T2 – Emerging Resources and Technologies|
|Published online||10 December 2014|
Study of an intrinsically safe infrastructure for training and research on nuclear technologies
1 INFN, Sezione di Genova, via Dodecaneso 33, Genoa 16146, Italy
2 Ansaldo Nucleare SpA, C.so F.M. Perrone 25, Genoa 16152, Italy
3 ENEA, via Martiri di Monte Sole, 4, Bologna 40129, Italy
4 ENEA, via Enrico Fermi, 45, Frascati (Rome) 00044, Italy
5 INFN, Sezione di Bari, via E. Orabona n. 4, Bari 70125, Italy
6 INFN, Laboratori Nazionali di Frascati, via Enrico Fermi, 40, Frascati (Rome) 00044, Italy
7 INFN Laboratori Nazionali di Legnaro, Viale dell'Università 2, Legnaro (Padova) 35020, Italy
8 INFN Laboratori Nazionali del Sud, via S. Sofia 62, Catania 95125, Italy
9 INFN, Sezione di Milano Bicocca e Università di Milano Bicocca, Piazza dell'Ateneo Nuovo, 1, Milan 20126, Italy
10 Lomonosov Moscow State University, GSP-1, Leninskie Gory, Moscow 119991, Russian Federation
11 Politecnico di Milano, Piazza L. da Vinci, 32, Milan 20133, Italy
12 Politecnico di Torino, Corso Duca degli Abruzzi, 24, Turin 10129, Italy
13 DIME – Università di Genova, via all'Opera Pia, 15/A, Genoa 16145, Italy
14 Università di Pavia and LENA, via Aselli 41, Pavia 27100, Italy
a Corresponding author: email@example.com
Published online: 10 December 2014
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.
© Owned by the authors, published by EDP Sciences, 2014
This is an Open Access article distributed under the terms of the Creative Commons Attribution License 4.0, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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