Results 61 to 70 of about 1,037 (124)
Statistical Analysis of Tritium Breeding Ratio Deviations in the DEMO Due to Nuclear Data Uncertainties [PDF]
, 2021 For the stable and self-sufficient functioning of the DEMO fusion reactor, one of the most important parameters that must be demonstrated is the Tritium Breeding Ratio (TBR).
Konobeev, Alexandre +3 more
core +2 more sources
Long-term corrosion behavior of ODS-Eurofer in flowing Pb-15.7Li at 550°C
Nuclear Materials and Energy, 2016 Low activation ferritic-martensitic steels (RAFM-steels) are foreseen as structural materials in different blanket designs (HCLL, DCLL, WCLL) with Pb-15.7Li as breeding and partly also as cooling medium.
W. Krauss, S.-E. Wulf, J. Konys
doaj +1 more source
Energies, 2023 Within the EUROfusion roadmap for the technological development of the European-DEMOnstration (EU-DEMO) reactor, a key point has been identified in the discontinuous operation (pulse-dwell-pulse) of the machine.
Alessandra Vannoni +14 more
doaj +1 more source
Fusion Engineering and Design, 2022 The EU-DEMO Water-Cooled Lithium-Lead (WCLL) Breeding Blanket (BB) main subsystems to be cooled are the Breeder Zone (BZ) and the First Wall (FW). Each subsystem will be equipped with an independent Primary Heat Transfer System (PHTS). Within the framework of the EUROfusion Work Package Breeding Blanket research program, several accidents belonging to ...
C. Ciurluini +4 more
openaire +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
Modeling the Transport of Activated Corrosion Products in the WCLL PbLi Loop for ITER and the EU DEMO With the GETTHEM Code [PDF]
, 2023 This work presents the results of the implementation in the GEneral Tokamak THErmal-hydraulic Model of available models for the generation and transport of any dispersed material in flowing PbLi eutectic mixture.
Arena, Pietro +6 more
core +2 more sources
Fusion Engineering and Design, 2021 Abstract Tritium permeation from breeder material to the Water Coolant System (WCS) in Water Cooled Lithium Lead (WCLL) Breeding Blanket (BB) is one of the technological issues to be solved in the design of the European DEMO. Since the tritium extraction from the Water Coolant System is more challenging and expensive than the extraction from the ...
Marco Utili +16 more
openaire +3 more sources
Multiphysics Optimization for Water-Cooled Breeding Blanket Design Enhancement [PDF]
, 2021 The commercial feasibility of the first fusion power plant generation adopting D-T plasma is strongly dependent upon the self-sustainability in terms of tritium fueling.
FORTE, Ruggero
core
Study of the thermo-mechanical performances of the EU-DEMO Water-Cooled Lead Lithium Left Outboard Blanket segment [PDF]
, 2023 The development of a sound conceptual design for the Water-Cooled Lead Lithium Breeding Blanket (WCLL BB) is pivotal to make a breakthrough towards the selection of the driver blanket concept for the EU-DEMO.
Arena P. +8 more
core +1 more source
Development of load specifications for the design of the breeding blanket system [PDF]
, 2020 The Breeding Blanket (BB) system with a volume of about 1700m(3) and a plasma front surface of about 1400m(2) represents the largest In-Vessel component of DEMO reactor. Due to its position and its key functions (e.g.
Boccaccini L. V. +4 more
core +1 more source