Embrittlement of WCLL blanket and its fracture mechanical assessment [PDF]
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 +7 more sources
Design of the Test Section for the Experimental Validation of Antipermeation and Corrosion Barriers for WCLL BB [PDF]
Applied Sciences (Switzerland), 2022 Tritium permeation into the Primary Heat Transfer System (PHTS) of DEMO and ITER reactors is one of the challenging issues to be solved in order to demonstrate the feasibility of nuclear fusion power plants construction.
M Utili, Ciro Alberghi, Luigi Candido
exaly +6 more sources
The Design of Water Loop Facility for Supporting the WCLL Breeding Blanket Technology and Safety [PDF]
Energies, 2023 The WCLL Breeding Blanket of DEMO and the Test Blanket Module (TBM) of ITER require accurate R&D activities, i.e., concept validation at a relevant scale and safety demonstrations. In view of this, the strategic objective of the Water Loop (WL) facility,
Alessandra Vannoni +16 more
doaj +8 more sources
Magneto-Convective Analyses of the PbLi Flow for the EU-WCLL Fusion Breeding Blanket
Energies, 2021 The Water Cooled Lithium Lead (WCLL) breeding blanket is one of the driver blanket concepts under development for the European Demonstration Reactor (DEMO). The majority of the blanket volume is occupied by flowing PbLi at eutectic composition.
F R Urgorri +2 more
exaly +4 more sources
Design of a Prototypical Mock-Up for the Experimental Investigation of WCLL First-Wall Performances [PDF]
Energies, 2023 A large research effort is currently ongoing within the framework of the EUROfusion consortium for the study and design of a water-cooled lithium–lead (WCLL) breeding blanket (BB).
Pietro Maccari +4 more
doaj +3 more sources
NUCLEAR DATA SENSITIVITY/UNCERTAINTY PRE-ANALYSIS OF FNG WCLL FUSION BENCHMARK [PDF]
EPJ Web of Conferences, 2021 To assure tritium self-sufficiency in future fusion reactors such as DEMO the accuracy of TRP calculations has to be demonstrated within the design uncertainties.
Kodeli Ivan A. +2 more
doaj +3 more sources
Modelling WCLL breeder blankets
, 2021 International audienceThe key purpose of DEMO is to provide electricity from fusion power. An integral part to this design will be the tritium breeding blanket. Accurate modelling of hydrogen transport and inventories within the breeder blanket component
Grisolia, Christian +6 more
core +3 more sources
Oxidation behaviour of EUROFER-97 under simulated water-cooled lithium lead breeder blanket conditions [PDF]
npj Materials DegradationThe effect of water chemistry, surface condition, alkalizing agent (LiOH vs. KOH), and Zn addition was investigated at 300 °C on the oxidation behaviour of reduced activation ferritic martensitic (RAF/M) EUROFER-97.
Liberato Volpe +4 more
doaj +2 more sources
Investigation of the DEMO WCLL Breeding Blanket Cooling Water Activation [PDF]
Fusion Engineering and Design, 2020 Within the framework of the activities foreseen by the EUROfusion action on the cooling water activation assessment for a DEMO reactor equipped with a Water Cooled Lithium Lead Breeding Blanket (WCLL BB), the University of Palermo is involved in the ...
Federici G. +9 more
core +6 more sources
Model Development and Transient Analysis of the WCLL BB BOP DEMO Configuration Using the Apros System Code [PDF]
Energies, 2021 Extensive modelling and analytical work has been carried out considering the water-cooled lithium–lead breeding blanket (WCLL BB) balance of plant (BOP) configuration of the demonstration power plant (DEMO) using the Apros system code, developed by VTT ...
Marton Szogradi, Sixten Norrman
doaj +2 more sources