Results 41 to 50 of about 119 (88)
Nuclear Materials and Energy, 2021 Tritium self-sufficiency presents a critical engineering challenge for DEMO, requiring efficient breeding and extraction systems, as well as minimizing tritium losses to the surrounding systems, such as plasma-facing components, vacuum vessel, cooling ...
R. Arredondo +3 more
doaj +1 more source
Nuclear Materials and Energy, 2020 The contribution of ENEA together with Rina-CSM to the Eurofusion programme “WPMAT-Advanced Seels” deals with the development of innovative RAFM steels able to withstand the critical temperatures typical of the different operational environments foreseen
C. Cristalli +3 more
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Nuclear Materials and Energy, 2022 Tritium self-sufficiency is a key requirement for future fusion power plants. Therefore, it will be necessary to minimize tritium losses to the surrounding systems, such as the tritium breeding modules, plasma-facing components, cooling system, etc ...
R. Arredondo +4 more
doaj +1 more source
Fusion Engineering and Design, 2021 Abstract The Water-Cooled Lithium Lead (WCLL) breeding blanket is one of the European blanket designs proposed for DEMO reactor. Tritium can permeate into the different structural materials, arising potential issues concerning the fuel self-sufficiency and can be lost into the environment with consequent radiological hazard for the population. Within
Candido, Luigi +6 more
openaire +1 more source
Embrittlement of WCLL blanket and its fracture mechanical assessment
Nuclear Fusion, 2023 In the European fusion programme, the Water Cooled Lithium Lead breeding blanket (WCLL BB) uses EUROFER as a structural material cooled with water at temperatures between 295 °C–328 °C and a pressure of 155 bar.
Jarir Aktaa +7 more
doaj +1 more source
Experimental and Numerical Results of LIFUS5/Mod3 Series E Test on In-Box LOCA Transient for WCLL-BB
Energies, 2021 The in-box LOCA (Loss of Coolant Accident) represents a major safety concern to be addressed in the design of the WCLL-BB (water-cooled lead-lithium breeding blanket).
Marica Eboli +5 more
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Recent Progress in the WCLL Breeding Blanket Design for the DEMO Fusion Reactor
IEEE Transactions on Plasma Science, 2018 The water-cooled lithium-lead (PbLi) breeding blanket is one of the candidate systems considered for the implementation in the European Demonstration Power Plant (DEMO) nuclear fusion reactor. This concept employs PbLi liquid metal as tritium breeder and neutron multiplier, water pressurized at 15.5 MPa as the coolant, and EUROFER as the structural ...
Alessandro Tassone +16 more
openaire +4 more sources
R&D Needs for the Design of the EU-DEMO HCPB ICD Balance of Plant in FP9
Journal of Nuclear Engineering, 2022 During the Pre-Conceptual Design Phase of the EU-DEMO, two BOP solutions for WCLL and HCPB were elaborated, as close as possible to industrial standards.
Sara Perez-Martin +3 more
doaj +1 more source
Mechanical Engineering Journal, 2023 In the framework of the development of fusion energy, one of the most prominent technologies arising to address the issues of tritium breeding and power conversion is the Water-Cooled Lithium-Lead (WCLL).
Nicolò BADODI +3 more
doaj +1 more source
Manufacturing of PAV-ONE, a Permeator against Vacuum Mock-Up with Niobium Membrane
Energies, 2023 The Permeator Against Vacuum (PAV) is one of the proposed technologies for the Tritium Extraction System of the WCLL BB (Water-Cooled Lithium-Lead Breeding Blanket) of the EU DEMO reactor.
Francesca Papa +8 more
doaj +1 more source