Experimental investigation and SIMMER-III code modelling of LBE–water interaction in LIFUS5/Mod2 facility

Pesetti, Alessio; Nevo, Alessandro Del; Forgione, Nicola

doi:10.1016/j.nucengdes.2014.11.016

Cited by 40 publications

(11 citation statements)

References 3 publications

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“…At the end of the water line, an injector is placed with a variable orifice (from 4 to 12 mm depending on the test), covered by a protective cap, which is broken by the increasing pressure at the beginning of the injection phase. The THINS experimental campaign [22][23][24][25][26][27] provided high quality data, based on well-defined boundary and initial conditions, for thermo-hydraulic characterization of the HLM/water interaction occurring after injecting water at 16 and 40 bar, from 180 to 240 • C, into a small pool of LBE at a higher temperature. The data obtained on pressure, temperature, strain, water level, and mass flow rate time trends permitted enlarging the experimental database and improving the knowledge of the phenomena.…”

Section: Separate Effect Tests On Hlm/water Interactionmentioning

confidence: 99%

Overview on Lead-Cooled Fast Reactor Design and Related Technologies Development in ENEA

et al. 2021

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The next generation of nuclear energy systems, also known as Generation IV reactors, are being developed to meet the highest targets of safety and reliability, sustainability, economics, proliferation resistance, and physical protection, with improved performances compared with the currently licensed plants or those presently being built. Among the proposed technologies, lead-cooled fast reactors (LFRs) have been identified by nuclear industries in both Western and developing countries as being among the optimal Generation IV candidates. Since 2000, ENEA, the Italian National Agency for New Technologies, Energy, and Sustainable Economic Development is supporting the core design, safety assessment, and technological development of innovative nuclear systems cooled by heavy liquid metals (HLM) and, most recently, fully oriented on LFRs. ENEA is developing world-recognized skills in fast spectrum core design and is one of the largest European fleets of experimental facilities aiming at investigating HLM thermal-hydraulics, coolant chemistry control, corrosion behavior for structural materials, and material properties in the HLM environment, as well as at developing corrosion-protective coatings, components, instrumentation, and innovative systems, supported by experiments and numerical tools. Efforts are also dedicated to develop and validate numerical tools for specific application to HLM systems, ranging from neutronics codes, system and core thermal-hydraulic codes, computational fluid dynamics (CFD) and fuel pin performance codes, including their coupling. The present work aims at highlighting the capabilities and competencies developed by ENEA so far in the framework of liquid metal technologies for Generation IV LFRs. In particular, an overview on the ongoing R&D experimental program will be depicted considering the current fleet of facilities, namely: CIRCE, NACIE-UP, LIFUS5, LECOR, BID-1, HELENA, RACHEL, and Mechanical Labs. An overview on the numerical activities performed so far and those presently ongoing is also reported. Finally, an overview of the ENEA contribution to the ALFRED Project in the frame of the FALCON international consortium is reported, mainly addressing the ongoing activity in terms of core design, technology development, and auxiliary systems design.

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Section: Separate Effect Tests On Hlm/water Interactionmentioning

confidence: 99%

Overview on Lead-Cooled Fast Reactor Design and Related Technologies Development in ENEA

et al. 2021

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“…The LIFUS5/Mod3 test facility is an upgraded version of the existing LIFUS5/Mod2 test facility (fully referenced in refs. [10] and [11]). In the new version, the facility was developed to two separate sections A and B.…”

Section: Lifus5/mod3 Test Facilitymentioning

confidence: 99%

Post-test analysis of Series D experiments in LIFUS5/Mod3 facility for SIMMER code validation of WCLL-BB In-box LOCA

Moghanaki

Galleni

Eboli

et al. 2021

Fusion Engineering and Design

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“…LIFUS5/Mod3 is a separate effect test facility that consists of modifying the existing LIFUS5/Mod2 test facility (see refs. [14]and [15] for more details) with a new smaller reaction vessel (S1B). The "section B" of the facility applies the S1B vessel and will be used in the framework of EUROfusion program, to investigate the PbLi-water interaction, Fig.…”

Section: Facility Descriptionmentioning

confidence: 99%

Analysis of Test D1.1 of the LIFUS5/Mod3 facility for In-box LOCA in WCLL-BB

Moghanaki

Galleni

Eboli

et al. 2020

Fusion Engineering and Design

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Experimental investigation and SIMMER-III code modelling of LBE–water interaction in LIFUS5/Mod2 facility

Cited by 40 publications

References 3 publications

Overview on Lead-Cooled Fast Reactor Design and Related Technologies Development in ENEA

Overview on Lead-Cooled Fast Reactor Design and Related Technologies Development in ENEA

Post-test analysis of Series D experiments in LIFUS5/Mod3 facility for SIMMER code validation of WCLL-BB In-box LOCA

Analysis of Test D1.1 of the LIFUS5/Mod3 facility for In-box LOCA in WCLL-BB

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