Results 81 to 90 of about 506,130 (104)

Dynamic thermal-hydraulic modelling of the EU DEMO WCLL breeding blanket cooling loops

, 2016
A global, system-level thermal-hydraulic model of the EU DEMO tokamak fusion reactor is currently under development and implementation in a suitable software at Politecnico di Torino, including the relevant heat transfer and fluid dynamics phenomena ...
A. Froio, F. Casella, F. Cismondi, A. Del Nevo, L. Savoldi, R. Zanino   +5 more
semanticscholar   +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

Fusion engineering and design, 2023
C. Ciurluini, A. Vannoni, Tommaso Del Moro, P. Lorusso, A. Tincani, A. Del Nevo, L. Barucca, F. Giannetti   +7 more
semanticscholar   +1 more source

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

On the impact of Lithium Diffusion on the Neutron Activation of Alumina Coatings in the DEMO WCLL Breeding Blanket

Conference paper presented at PHYSOR 2026 - The International Conference on Physics of Reactors. Published in Proceedings of PHYSOR 2026 International Conference. ISBN: 979-12-81583-46-7. Conference website: https://www.physor2026.org/. Session: S02. Neutronics for Fusion. Paper ID: 658. Copyright transferred to Politecnico di Torino by the authors for
L. Piccinini, A. Stinchelli, F. Di Fonzo, V. Mascolino, N. Cefis   +4 more
openaire   +2 more sources

A novel chemical reaction model for safety analysis of lithium–lead/water interaction in water cooled lithium lead breeding blankets using SIMMER code

Nuclear Fusion
The water cooled lithium lead breeding blanket (BB) stands out as one of the most promising designs for future fusion reactor BBs. However, the significant interaction between water and lithium–lead, particularly triggered by an In-Box LOCA (Loss of ...
V. Cossu, C. Risi, F. Galleni, M. Eboli, A. Del Nevo, N. Forgione, K. Morita   +6 more
doaj   +1 more source

Engineering challenges for accelerated fusion demonstrators. [PDF]

Philos Trans A Math Phys Eng Sci, 2019
Surrey E.
europepmc   +1 more source

Numerical analyses in support of the in-box LOCA experimental campaign for the WCLL Breeding Blanket design

In the framework of the advanced design of the European DEMO nuclear fusion reactor, the Water-Cooled Lithium Lead (WCLL) concept represents one of the most promising options for the Breeding Blanket (BB) technology. Based on this assessment, the WCLL BB
COSCI, MARCO
core