Fusion technologies development at ENEA Brasimone Research Centre: Status and perspectives

Tarantino, M.; Martelli, Daniele; Nevo, Alessandro Del; Utili, Marco; Piazza, Ivan Di; Eboli, Marica; Diamanti, D.; Tincani, A.; Miccichè, G.; Bernardi, D.; Nitti, Francesco; Cristalli, C.; Bassini, Serena; Fiore, Angela; Cataldo, Sebastiano; Sartorio, Camillo; Venturini, Alessandro; Marinari, R.; Lorusso, Pierdomenico

doi:10.1016/j.fusengdes.2020.112008

Cited by 12 publications

(5 citation statements)

References 47 publications

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“…Within the EUROfusion Work Package Balance of Plant task, an experimental campaign was executed as part of the research activities undertaken at ENEA Brasimone R.C. to investigate the PbLi technology [29][30][31]. A test matrix of five tests was set up for the CIRCE-HERO facility in order to obtain experimental data in operating conditions relevant for the PbLi/water HEX [12] of the EU DEMO fusion reactor.…”

Section: Eurofusion Experimental Campaignmentioning

confidence: 99%

Experimental Investigation on CIRCE-HERO for the EU DEMO PbLi/Water Heat Exchanger Development

et al. 2021

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The present paper describes the experimental campaign executed at the ENEA Brasimone Research Centre aiming at supporting the development of a PbLi/water heat exchanger suitable for the lithium–lead loops of the dual coolant lithium lead and the water cooled lithium lead breeding blankets of the EU DEMO fusion reactor. The experiments were performed in a test section named HERO, installed inside the main vessel of the lead–bismuth eutectic-cooled pool-type facility CIRCE. The test section hosts a steam generator bayonet tube mock-up in relevant scale, which was selected as a promising configuration for DEMO purposes. For the thermal-hydraulic characterization of the component, five tests were executed at different water pressures (6, 8, 12 MPa, two tests at 10 MPa), and liquid metal flow rates (40, 33, 27, 20, 10 kg/s). The experimental outcomes proved the technological feasibility of this novel steam generator and its suitability for the DEMO PbLi loops. The activity was completed with a post-test analysis using two versions of the system code RELAP5. Because the experiments were executed with lead–bismuth eutectic, a scaling analysis is proposed to find the equivalence with PbLi. RELAP5 code was applied to recalculate the experimental data using PbLi as working fluid.

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Section: Eurofusion Experimental Campaignmentioning

confidence: 99%

Experimental Investigation on CIRCE-HERO for the EU DEMO PbLi/Water Heat Exchanger Development

et al. 2021

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“…The LIFUS5/Mod3 is a separate effect test facility, designed and constructed at ENEA CR Brasimone [15]. It can operate with different heavy liquid metals like Lead-Lithium and Lead-Bismuth eutectic alloys and pure lead.…”

Section: Lifus5/mod3 Facility Descriptionmentioning

confidence: 99%

“…The present work describes the results of Test D1.1, executed at ENEA C.R. Brasimone [15]. In particular, pressures, temperatures, amount of injected water, and hydrogen production quantification are reported and critically discussed.…”

Section: Introductionmentioning

confidence: 99%

Test Series D experimental results for SIMMER code validation of WCLL BB in-box LOCA in LIFUS5/Mod3 facility

Eboli

Crugnola

Cammi

et al. 2020

Fusion Engineering and Design

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“…As a partner of the EUROfusion Consortium, ENEA (Italian National Agency for New Technologies, Energy and Sustainable Economic Development) pursues R&D activities to develop the Water Cooled Lithium Lead (WCLL) Breeding Blanket (BB) design [5], selected as the driver concept for DEMO, in the framework of the BB and Balance of Plant (BoP) work packages of the EUROfusion Power Plant Physics and Technology Programme.…”

Section: Introductionmentioning

confidence: 99%

Development of a Steam Generator Mock-Up for EU DEMO Fusion Reactor: Conceptual Design and Code Assessment

et al. 2023

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Recent R&D activities in nuclear fusion have identified the DEMO reactor as the ITER successor, aiming at demonstrating the technical feasibility of fusion plants, along with their commercial exploitation. However, the pulsed operation of the machine causes an “unconventional” operation of the system, posing unique challenges to the functional feasibility of the steam generator, for which it is necessary to define and qualify a reference configuration for DEMO. In order to facilitate the transitions between different operational regimes, the Once Through Steam Generator (OTSG) is considered to be a suitable choice for the DEMO primary heat transfer systems, being characterized by lower thermal inertia with respect to the most common U-tube steam generators. In this framework, the ENEA has undertaken construction of the STEAM facility at Brasimone R.C., aiming at characterizing the behavior of the DEMO OTSG and related water coolant systems in steady-state and transient conditions. A dedicated OTSG mock-up has been conceived and designed, adopting a scaling procedure, keeping the height 1:1 of the DEMO OTSGs. The conceptual design has been supported by RELAP5/Mod3.3 thermal-hydraulic calculations. CFD and FEM codes have been used for fluid-dynamic analyses and mechanical stress analyses, respectively, in specific parts of the component.

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Fusion technologies development at ENEA Brasimone Research Centre: Status and perspectives

Cited by 12 publications

References 47 publications

Experimental Investigation on CIRCE-HERO for the EU DEMO PbLi/Water Heat Exchanger Development

Experimental Investigation on CIRCE-HERO for the EU DEMO PbLi/Water Heat Exchanger Development

Test Series D experimental results for SIMMER code validation of WCLL BB in-box LOCA in LIFUS5/Mod3 facility

Development of a Steam Generator Mock-Up for EU DEMO Fusion Reactor: Conceptual Design and Code Assessment

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