M. Utili
ENEA
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Publication
Featured researches published by M. Utili.
Fusion Science and Technology | 2011
I. Ricapito; Andrea Ciampichetti; R. Lässer; Y. Poitevin; M. Utili
Abstract Extraction of tritium from liquid lead lithium eutectic alloy is a key topic for the feasibility of any PbLi based tritium breeding blanket (BB). Particularly in DEMO, high tritium extraction efficiency will be required in order to keep low the tritium concentration in the Pb-16Li loop. This is essential to minimize tritium release into the environment and tritium permeation from BB into the primary cooling system. In addition, the tritium extraction process needs to be highly reliable in order not to impact negatively on the operation of the whole fusion reactor, ITER or DEMO. In the present paper, a critical review of the main candidate technologies for tritium extraction from Pb-16Li, particularly gas liquid contactors and vacuum permeators, is accomplished. The intrinsic limits and possible advantages of these technologies are presented and discussed, in the light of considerations coming directly from mathematical models describing their behaviour as well as from the experimental results so far achieved. Needs in terms of R&D activities are identified.
Fusion Science and Technology | 2015
I. Ricapito; P. Calderoni; Y. Poitevin; A. Aiello; M. Utili; D. Demange
Abstract Tritium processing technologies of the two European Test Blanket Systems (TBS), HCLL (Helium Cooled Lithium Lead) and HCPB (Helium Cooled Pebble Bed), play an essential role in meeting the main objectives of the TBS experimental campaign in ITER. The compliancy with the ITER interface requirements, in terms of space availability, service fluids, limits on tritium release, constraints on maintenance, is driving the design of the TBS tritium processing systems. Other requirements come from the characteristics of the relevant TBM and the scientific programme that has to be developed and implemented. This paper identifies the main requirements for the design of the TBS tritium systems and equipment and, at the same time, provides an updated overview on the current design status, mainly focusing onto the tritium extractor from Pb-16Li and TBS tritium accountancy. Considerations are also given on the possible extrapolation to DEMO breeding blanket.
Fusion Science and Technology | 2017
Vincenzo D’Auria; Sandra Dulla; Piero Ravetto; Laura Savoldi; M. Utili; Roberto Zanino
Abstract The current studies on the development of the EU DEMO breeding blanket include among the options the use of liquid Lithium-Lead (17Li-83Pb) as tritium breeder (and multiplier), with different coolants. As the tritium is steadily produced in the blanket during the reactor operation, suitably efficient strategies for the Tritium Extraction System (TES) from the breeder must be developed, allowing a closed fuel cycle in situ and avoiding tritium accumulation in the machine. The Permeator Against Vacuum (PAV) appears to be one of the most promising solutions to achieve this goal. In this paper, the performance of a PAV system is studied by means of different models describing the transport of tritium in the liquid PbLi and in the metallic membrane separating it from the vacuum. The comparison of the results for different membrane materials and size of the device, for a given target efficiency, allows to optimize the PAV design, also taking into account corrosion issues. The approximations and limitations of the adopted models are also addressed.
IEEE Transactions on Plasma Science | 2017
Luigi Candido; Iuri Nicolotti; M. Utili; Massimo Zucchetti
A new design of a hydrogen sensor for Pb-16Li, based on the previous experience and testing results, is performed. The new permeation sensor is made of pure iron. The intention of this optimized design is to improve the response time and to minimize the number of welds to be made. Some simulations were conducted to estimate the time taken for the sensor to reach equilibrium with the partial pressure of hydrogen in the lead–lithium. With respect to the old sensor design, the diameter of the steel connection pipe has been reduced, while its length has been increased. In this way, it was possible to reduce the dead volume within the sensor and increase the permeation area, giving the sensor a faster time response.
Fusion Engineering and Design | 2016
L.V. Boccaccini; G. Aiello; J. Aubert; C. Bachmann; T. Barrett; A. Del Nevo; D. Demange; L. Forest; Francisco Andrés León Hernández; P. Norajitra; G. Porempovic; David Rapisarda; P. Sardain; M. Utili; L. Vala
Fusion Engineering and Design | 2017
A. Del Nevo; Emanuela Martelli; P. Agostini; P. Arena; G. Bongiovì; Gianfranco Caruso; G. Di Gironimo; P.A. Di Maio; Marica Eboli; R. Giammusso; Fabio Giannetti; A. Giovinazzi; G. Mariano; F. Moro; Rocco Mozzillo; Alessandro Tassone; Davide Rozzia; Andrea Tarallo; Mariano Tarantino; M. Utili; R. Villari
Journal of Nuclear Materials | 2007
Andrea Ciampichetti; Massimo Zucchetti; Italo Ricapito; M. Utili; A. Aiello; G. Benamati
symposium on fusion technology | 2007
A. Aiello; Andrea Ciampichetti; M. Utili; G. Benamati
symposium on fusion technology | 2009
A. Aiello; M. Utili; S. Scalia; G. Coccoluto
symposium on fusion technology | 2007
I. Ricapito; A. Aiello; Andrea Ciampichetti; G. Benamati; M. Utili; Massimo Zucchetti