Results 41 to 50 of about 78 (65)

Thermal-hydraulic analysis of WCLL BB First-Wall mock-up in Water Loop facility under transient conditions

Fusion Engineering and Design
The EUropean DEMOnstration Power Plant (EU-DEMO) represents a milestone in nuclear fusion research, serving as crucial step towards the realization of commercial fusion energy production by bridging the gap between current research efforts and future industrial-scale deployment.
Mongiardini, G., Vannoni, A., Ciurluini, C., Maccari, P., Gonfiotti, B., Arena, P., Eboli, M., Giannetti, F., Nevo, A. Del   +8 more
openaire   +1 more source

The chemical compatibility of oxide ceramic candidates in static PbLi for advanced breeding blanket channel components

Nuclear Materials and Energy
The use of a PbLi eutectic alloy is extended in the Dual Coolant Lead Lithium (DCLL) and Water Coolant Lead Lithium (WCLL) Breeding Blanket (BB) design concepts in future fusion reactors.
J. Patiño, J.M García, G.D. Soria, M. González   +3 more
doaj   +1 more source

Investigation on MELCOR Code Capabilities for the Simulation of Lithium–Lead Chemical Interactions for Fusion Safety Applications

Energies
In the WCLL-BB liquid blanket concept, among the postulated accidental scenarios to be investigated regarding the PbLi system, a loss of liquid metal is one of the most crucial for safety purposes.
Francesco Galleni, Vittorio Cossu, Marigrazia Moscardini, Nicola Forgione   +3 more
doaj   +1 more source

Deterministic analysis of residual heat removal from activated EU DEMO WCLL BB segments during ex-vessel LOCA

Fusion Engineering and Design
Bibliografija: str. 11.
Draksler, Martin, Končar, Boštjan, Bachmann, Christian, Moscato, Ivo, Ciattaglia, Sergio, Valentine, Alex   +5 more
openaire   +2 more sources

Thermal-hydraulic pre-test analysis of the WCLL BB TBM mock-up in view of the experimental campaign to be performed in Water Loop facility

Fusion Engineering and Design
The Breeding Blanket is a key component of a fusion reactor, responsible for shielding structures outside the plasma chamber, closing the fuel cycle by producing tritium, and removing the heat generated by the fusion reaction. Among the designs proposed for the EUropean DEMOnstration fusion power plant (EU-DEMO) aimed at bridging current research and ...
G. Mongiardini, C. Ciurluini, B. Gonfiotti, A. Vannoni, N. Badodi, P. Arena, M. Eboli, F. Giannetti, A. Del Nevo   +8 more
openaire   +1 more source

Modelling LOFA scenario for WCLL BB concept using MELCOR1.8.5 code

Fusion Engineering and Design, 2023
Khani, Samad, Scraggs, David, Roberts, Lois, Perry, David   +3 more
openaire   +1 more source

A novel chemical reaction model for safety analysis of lithium–lead/water interaction in water cooled lithium lead breeding blankets using SIMMER code

Nuclear Fusion
The water cooled lithium lead breeding blanket (BB) stands out as one of the most promising designs for future fusion reactor BBs. However, the significant interaction between water and lithium–lead, particularly triggered by an In-Box LOCA (Loss of ...
V. Cossu, C. Risi, F. Galleni, M. Eboli, A. Del Nevo, N. Forgione, K. Morita   +6 more
doaj   +1 more source

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Integration of LiPb loops for WCLL BB of European DEMO

Fusion Engineering and Design, 2021
Abstract The eutectic alloy Lithium Lead (LiPb) enriched at 90 % in 6Li is the breeder material for one of the candidate European Breeding Blanket (BB) concepts. Currently under investigation for DEMO reactor, the Water Cooled Lithium-Lead (WCLL), and for the WCLL Test Blanket Module (TBM) that will be qualified in the ITER reactor. The LiPb alloy is
Mozzillo, Rocco, Utili, Marco, Venturini, Alessandro, Tincani, Amelia, Gliss, Curt   +4 more
openaire   +2 more sources

Experimental activities for in-box LOCA of WCLL BB in LIFUS5/Mod3 facility

Fusion Engineering and Design, 2019
Abstract The new experimental facility LIFUS5/Mod3 has been designed, manufactured and installed to investigate the phenomena connected with the thermodynamic and chemical interaction between lithium-lead and water in case of in-box LOCA (Loss of Coolant Accident) of the WCLL breeding blanket concept and to validate the chemical model implemented in ...
Eboli M., Moghanaki S. K., Martelli D., Forgione N., Porfiri M. T., Del Nevo A.   +5 more
openaire   +2 more sources

Tritium Extraction From HCLL/WCLL/DCLL PbLi BBs of DEMO and HCLL TBS of ITER

IEEE Transactions on Plasma Science, 2019
The tritium balance in DEMO reactor is a key factor for the success of the production of energy from the thermonuclear fusion reactor. Three of the four breeder blankets (BBs) concepts candidates for DEMO used the eutectic Pb–16Li enriched at 90% in 6Li as breeder, the water-cooled lithium–lead, dual-coolant lithium–lead, and helium-cooled lithium–lead
Marco Utili, Amelia Tincani, Luigi Candido, Laura Savoldi, Roberto Zanino, Massimo Zucchetti, Daniele Martelli, Alessandro Venturini   +7 more
openaire   +2 more sources