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Assessment of the relevancy of ENEA water loop facility with respect to ITER WCLL TBS water cooling system by considering their thermal-hydraulic performances [PDF]

The Water -Cooled Lead -Lithium (WCLL) is one of the two candidate concepts for the Breeding Blanket (BB) of DEMO. A Test Blanket Module (TBM) together with its Water Cooling System (WCS) is going to be installed and tested in the ITER reactor.
Arena, P. +4 more
core +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

DEMO Breeding Blanket Concepts in EUROfusion work package breeding blanket (WPBB) [PDF]

, 2021
Hernández, Francisco A ., Zhou, Guangming +1 more
core +2 more sources

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

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 +6 more
doaj +1 more source

Engineering challenges for accelerated fusion demonstrators. [PDF]