D. Bernardi
ENEA
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Featured researches published by D. Bernardi.
ieee symposium on fusion engineering | 2013
P. Arena; D. Bernardi; G. Bongiovì; P. A. Di Maio; Manuela Frisoni; G. Miccichè; M. Serra
In the framework of the current IFMIF Engineering Validation and Engineering Design Activities (IFMIF/EVEDA) phase, ENEA is responsible for the design of the European concept of the IFMIF lithium target system which foresees the possibility to periodically replace only the most irradiated and thus critical component (i.e., the backplate) while continuing to operate the rest of the target for a longer period (bayonet backplate concept). In this work, the results of the steady state thermomechanical analysis of the IFMIF EU target assembly are briefly reported highlighting the relevant indications obtained with respect to the fulfillment of the design requirements.
ieee symposium on fusion engineering | 2013
G. Miccichè; D. Bernardi; F. Tagliaferri; P. A. Di Maio
The International Fusion Materials Irradiation Facility (IFMIF) will be equipped with a lithium target assembly to produce the required neutron flux for the irradiation of candidate fusion materials up to a damage rate of 100 dpa (cumulated damage in five years). The present European target assembly design is based on the so called replaceable backplate bayonet concept that was developed with the objective to simplify the maintenance operations for its refurbishment/replacement and to reduce the material for disposal as well. To this purpose it was also conceived to be attached to the lithium pipes and to the beam line by means of remotely operated connections based on clamped flanges with sealing metal gaskets. Accordingly, a custom design of this remotely operated connection, named Fast Disconnecting System (FDS), has been developed for the inlet flanged connections of the European IFMIF target assembly system. So far similar systems, already commercially available, have been used for several types of applications including nuclear ones, although never used neither under the IFMIF-like operating conditions nor fully remotely. The FDS is based on a commercial chain, which provides the required tightening force for the sealing of the edge of the flanges, that can be locked/unlocked by means of a reduced number of screws. The designed FDS prototype is provided with several additional features, to satisfy the operational working condition foreseen for IFMIF in terms of functionalities, safety and maintainability, like: the lithium leakage system; the flanges detachment mechanism; the insulation system and the systems to open the chain or to release the FDS in case of failure. A prototype of the FDS has been manufactured and based on the preliminary tests carried out the suitability to remote handling of the system has been proved. In this paper a description of the design of the FDS together with the outcomes of the remote handling validation tests are given.
18th International Conference on Nuclear Engineering: Volume 4, Parts A and B | 2010
Mariano Tarantino; D. Bernardi; G. Coccoluto; P. Gaggini; Valerio Labanti; Nicola Forgione; Andrea Napoli
The paper reports on the results carried out from the natural circulation and gas-injection enhanced circulation tests performed on a heavy liquid metal loop, named NACIE, and located by the Brasimone ENEA Research Centre. The work is aimed at providing information on the characterization and interpretation of the basic mechanisms proposed in the design of future reactor relying on these circulation mechanisms. The results discussed in the present work concern the experiments performed using Lead Bismuth Eutectic (LBE) as coolant. Both natural circulation and gas-injection enhanced have been addressed, drawing conclusions about the observed phenomena. Numerical simulations have been performed in collaboration with the University of Pisa, adopting the RELAP5/Mod3.3 system code modified to allow for LBE as a cooling fluid. Post-test calculations have been performed to compare the code response with the experimental results under the natural circulation and gas enhanced circulation flow regime, allowing to qualify the adopted nodalisation as well as the performance of the code when employed on HLM loop. The available data will allow to validate and qualify numerical tools for engineering application, establishing a reference experiment for the benchmark of commercial codes when employed in HLM loop.Copyright
18th International Conference on Nuclear Engineering (ICONE18) | 2010
D. Bernardi; Andrea Ciampichetti; Mariano Tarantino; G. Coccoluto; Nicola Forgione; Francesco Poli; Marco Catanorchi
In the framework of the research activities of the EURATOM FP6 project named ELSY (European Lead-cooled System), aimed at demonstrating the possibility of designing a competitive and safe fast critical reactor based on the Generation IV Lead Fast Reactor (LFR) concept, the study of the lead-water interaction following an incidental SGTR (Steam Generator Tube Rupture) event is an important issue to address. To simulate such event, an experimental test has been carried out on the LIFUS 5 facility at the ENEA Brasimone Research Centre, in order to assess the physical effects and the possible consequences connected to this kind of interaction. The experiment has been conducted by injecting water at the pressure of 185 bar and with a temperature of 300 °C into a volume of 80 l of Lead Bismuth Eutectic (LBE) kept at atmospheric pressure and at a temperature of 400 °C. The experimental facility has been suitably modified in order to reproduce as close as possible the operating conditions of the ELSY Steam Generator Unit (SGU), in which a free volume of cover gas (argon) is foreseen at the top of the system, with the objective to dampen the pressure waves inside the SGU itself. The experimental test has been supported through a numerical modelling campaign performed at the University of Pisa by means of the SIMMER code within both 2-D (SIMMER III) and 3-D (SIMMER IV) models. Pre-test simulations have been carried out to aid the design of the new facility configuration and to select the test conditions which could better reproduce the behaviour expected for ELSY. In addition, a post-test analysis has also been accomplished, allowing to compare the numerical and experimental results, so as to validate and assess the performance of the code when employed for this kind of applications.Copyright
Fusion Engineering and Design | 2014
J. Knaster; D. Bernardi; A. García; F. Groeschel; R. Heidinger; Mizuho Ida; A. Ibarra; G. Micchiche; S. Nitti; M. Sugimoto; E. Wakai
Fusion Engineering and Design | 2013
P. Arena; D. Bernardi; G. Bongiovì; P.A. Di Maio; G. Miccichè
Journal of Nuclear Materials | 2011
Andrea Ciampichetti; D. Bernardi; T. Cadiou; Nicola Forgione; Francesco Poli; D. Pellini
Fusion Engineering and Design | 2011
D. Bernardi; P. Agostini; G. Miccichè; F.S. Nitti; A. Tincani
Fusion Engineering and Design | 2015
D. Bernardi; P. Arena; G. Bongiovì; P.A. Di Maio; Manuela Frisoni; G. Miccichè; M. Serra
Fusion Engineering and Design | 2014
Manuela Frisoni; D. Bernardi; G. Miccichè; M. Serra