Results 1 to 10 of about 119 (88)

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

On the evaluation of the DEMO WCLL Breeding Blanket sector thermal-hydraulic performances at a system level

Fusion Engineering and Design
To obtain an affordable BB design, one of the key issues is assessing its thermal-hydraulic performances during operational and accidental conditions. For this, an analysis of the component transient behavior is needed to improve and refine the project.
Francesco Colliva, Fabio Giannetti, Antonio Trotta, Alessandro Del Nevo, Gianfranco Caruso, Cristiano Ciurluini   +5 more
openaire   +1 more source

Activated corrosion product contamination assessments of DEMO WCLL breeding blanket primary heat transport system

Fusion Engineering and Design
In water-cooled fusion reactors, the assessment of the primary system contamination is essential for waste management, machine availability, occupational radiation exposure, and radiological hazard determination. The primary cooling water is not only directly activated by the intense neutron field but is a contamination vector for a significant variety
Terranova, Nicholas, Chiovaro, Pierluigi, Dacquait, Frédéric, Moscato, Ivo, Vallone, Eugenio   +4 more
openaire   +3 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

Multiphysics tritium transport simulations of the WCLL breeding blanket for DEMO

Simulations multiphysiques du transport du tritium dans la couverture tritigène la WCLL pour OEMO Cette étude présente le développement d'un modèle multiphysique dont l'objectif et la simulation du transport du tritium dans la couverture tritigène de DEMO WCLL (Water Cooled Lithium Lead).
openaire   +2 more sources

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

The European roadmap towards fusion electricity. [PDF]

Philos Trans A Math Phys Eng Sci, 2019
Donné AJH.
europepmc   +1 more source