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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 +7 more sources
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 +5 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 +5 more sources
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.
Matteo D'Onorio +2 more
exaly +4 more sources
Fusion Engineering and Design, 2021 Abstract 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) that will be tested in the Test Blanket Module of the ITER reactor. In this accident, a tube rupture in the coolant circuit would cause a potential disruptive exothermic ...
Francesco Galleni +2 more
exaly +3 more sources
Analysis of Test D1.1 of the LIFUS5/Mod3 facility for In-box LOCA in WCLL-BB
Fusion Engineering and Design, 2020 Abstract The in-box Loss of Coolant Accident (LOCA) scenario is considered as one of the most affecting safety concerns for the Water-Cooled Lead Lithium Breeding Blanket (WCLL-BB) modules of the DEMOnstration (DEMO) reactor, which is sequentially followed by a multi-phase multi-component physical and chemical interaction.
Francesco Galleni +2 more
exaly +2 more sources
Fusion Engineering and Design, 2021 Abstract The In-box LOCA for the WCLL-BB is recognized as a Design Basis Accident (DBA) and is of substantial interest to the DEMOnestration reactor design, therefore, the transient response of such an accident must be carefully investigated and addressed to ensure the safe operation and integrity of the whole system.
Francesco Galleni +2 more
exaly +2 more sources
Fusion Engineering and Design, 2019 Abstract One of the four breeding blanket concepts for European DEMO nuclear fusion reactor is the Water-Cooled Lithium Lead Breeding Blanket (WCLL BB). The WCLL in-box LOCA (Loss Of Coolant Accident) is a major safety concern of this component, therefore transient behavior shall be investigated to support the design, to evaluate the consequences and
Marica Eboli +2 more
exaly +3 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