Results 1 to 10 of about 153,088 (155)
Experimental and Numerical Results of LIFUS5/Mod3 Series E Test on In-Box LOCA Transient for WCLL-BB [PDF]
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
doaj +3 more sources
Numerical Simulations with RELAP5-3D and RELAP5/mod3.3 of the Second Experimental Campaign on In-Box LOCA Transients for HCLL TBS [PDF]
Energies, 2021 In-box LOCA was identified as one of the worst accidental scenarios for the HCLL TBS (Helium Cooled Lithium-Lead Test Blanket System). Aiming to experimentally analyze the consequences of this transient, ENEA designed and built THALLIUM (Test HAmmer in ...
Alessandro Venturini +2 more
doaj +3 more sources
Application of Inelastic Method and Its Comparison with Elastic Method for the Assessment of In-Box LOCA Event on EU DEMO HCPB Breeding Blanket Cap Region [PDF]
Applied Sciences, 2021 The Helium Cooled Pebble Bed (HCPB) breeding blanket, being developed by the Karlsruhe Institute of Technology (KIT) and its partners is one of the two driver blanket candidates to be selected for the European demonstration fusion power plant (EU DEMO ...
Anoop Retheesh +2 more
doaj +3 more sources
Fusion Engineering and Design, 2020 Abstract The in-box LOCA (Loss of Coolant Accident) is a relevant safety issue for the design of the WCLL BB. Research activities are ongoing to master phenomena and processes occurring during the postulated accident, to enhance the predictive capability and reliability of numerical tools, and to validate computer models, codes and procedures for ...
Marica Eboli +2 more
exaly +2 more sources
PbLi/Water Reaction: Experimental Campaign and Modeling Advancements in WPBB EUROfusion Project
Energies, 2023 The Water-Cooled Lithium–Lead blanket concept is a candidate breeding blanket concept for the EU DEMO reactor and it is going to be tested as one of the Test Blanket Modules (TBM) inside the ITER reactor.
Marica Eboli +14 more
doaj +1 more source
Status, Features, and Future Development of the LIFUS5/Mod4 Experimental Facility Design
Applied Sciences, 2022 The Water-Cooled Lithium–Lead (WCLL) is one of the most promising technologies for power conversion and tritium production in future fusion-powered reactors; it will be implemented in one of the Test Breeding Modules (TBM) inside the ITER reactor and the
Nicolò Badodi +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
In-box LOCA accident analysis for the European DEMO water-cooled reactor [PDF]
Fusion Engineering and Design, 2019 Abstract Transient analyses in a water-cooled fusion DEMO (Demonstration Power Plant) reactor have been performed to support the WCLL (Water-Cooled Lithium Lead) breeding blanket design. In this framework, the Design Basis Accident (DBA) analysis of an in-box LOCA has been carried out.
D’Onorio, Matteo +3 more
openaire +1 more source
Preliminary Design of a Heat Pipe-Cooled Blanket for CFETR
Energies, 2021 Blankets are a difficult problem for fusion engineering design. Because of the complex flow channels, the design, production, processing, and accident maintenance of blankets are all huge challenges for traditional water/gas-cooled blankets. Blankets are
Dianle Wang, Yun Guo
doaj +1 more source
Applied Sciences, 2023 The Water-Cooled Lead Lithium (WCLL) Breeding Blanket (BB) is one of the two BB concept candidates to be selected as the driver blanket for the EU DEMO fusion reactor.
Gaetano Bongiovì +6 more
doaj +1 more source