Results 71 to 80 of about 502,482 (107)

Modelling an in-vessel loss of coolant accident in the EU DEMO WCLL breeding blanket with the GETTHEM code

Fusion Engineering and Design, 2018
Abstract One of the accidents to be analyzed for the operation of the EU DEMO tokamak reactor is the in-vessel Loss-Of-Coolant Accident (LOCA), in which a postulated rupture in the First Wall causes a rapid pressurization of the Vacuum Vessel (VV).
Froio, Antonio, Bertinetti, Andrea, Ciattaglia, Sergio, Cismondi, Fabio, Savoldi, Laura, Zanino, Roberto   +5 more
openaire   +2 more sources

Optimization of the breeder zone cooling tubes of the DEMO Water-Cooled Lithium Lead breeding blanket

, 2016
The determination of an optimal configuration for the breeder zone (BZ) cooling tubes is one of the most important issues in the DEMO Water-Cooled Lithium Lead (WCLL) breeding blanket R&D activities, since BZ cooling tubes spatial distribution should ...
CHIOVARO, Pierluigi, Bongiovì, Gaetano, ARENA, Pietro, Del Nevo, A., DI MAIO, Pietro Alessandro, FORTE, Ruggero   +5 more
core   +1 more source

Neutronics Simulations for DEMO Diagnostics. [PDF]

Sensors (Basel), 2023
Luís R, Nietiadi Y, Quercia A, Vale A, Belo J, Silva A, Gonçalves B, Malaquias A, Gusarov A, Caruggi F, Perelli Cippo E, Chernyshova M, Bienkowska B, Biel W.   +13 more
europepmc   +1 more source

Implications of T loss in first wall armor and structural materials on T-self-sufficiency in future burning fusion devices

Nuclear Fusion
Future fusion reactors will have to breed enough tritium (T) to sustain continuous operation and to produce excess T to power up other fusion reactors. Therefore, T is a scarce resource that must not be lost inside the fusion power plants systems.
K. Schmid, T. Schwarz-Selinger, R. Arredondo, A. Theodorou, T. Pomella Lobo   +4 more
doaj   +1 more source

Breeding blanket mock-up testing in IFMIF-DONES

Nuclear Fusion
The fusion community is looking for solutions to qualify the breeding blankets (BB) before their final testing in DEMO. Thus, ambitious and attractive proposals, like the Volumetric Neutron Source, are being explored.
D. Rapisarda, P. Arena, F. Arranz, B. Brañas, F. Mota, M.I. Ortiz, A. Serikov, G. Zhou   +7 more
doaj   +1 more source

Materials to Be Used in Future Magnetic Confinement Fusion Reactors: A Review. [PDF]

Materials (Basel), 2022
Alba R, Iglesias R, Cerdeira MÁ.
europepmc   +1 more source

Thermal-hydraulic assessment of Once-Through Steam Generators for EU-DEMO WCLL Breeding Blanket primary cooling system application

, 2023
Cristiano Ciurluini, Alessandra Vannoni, Tommaso Del Moro, Pierdomenico Lorusso, A. Tincani, Alessandro DEL NEVO, L. Barucca, Fabio Giannetti   +7 more
openalex   +2 more sources

The chemical compatibility of oxide ceramic candidates in static PbLi for advanced breeding blanket channel components

Nuclear Materials and Energy
The use of a PbLi eutectic alloy is extended in the Dual Coolant Lead Lithium (DCLL) and Water Coolant Lead Lithium (WCLL) Breeding Blanket (BB) design concepts in future fusion reactors.
J. Patiño, J.M García, G.D. Soria, M. González   +3 more
doaj   +1 more source

Optimized Water Distillation Layout for Detritiation Purpose

Applied Sciences
Tritium permeation constitutes a key issue for the future EU-DEMO, especially in the Breeding Blanket (BB) where fusion energy must be delivered to the Primary Heat Transport System (PHTS) and where tritium must be bred.
Vincenzo Narcisi, Alessia Santucci
doaj   +1 more source

System code simulation of DEMO WCLL central outboard blanket equatorial cell operational transients [PDF]

Within the framework of EUROfusion FP8 and FP9 research activities, an important work was carried out to optimize the DEMO Breeding Blanket (BB) layout. The blanket concept selected to be investigated in this work is the Water-Cooled Lead-Lithium (WCLL).
Del Nevo A., Principato M., Ciurluini C., Giannetti F.   +3 more
core   +1 more source