Results 101 to 110 of about 7,951 (222)
Calculating the 3D magnetic field of ITER for European TBM studies
The magnetic perturbation due to the ferromagnetic test blanket modules (TBMs) may deteriorate fast ion confinement in ITER. This effect must be quantified by numerical studies in 3D.
Asunta, O +9 more
core +1 more source
Tritium breeding and activation in the cascade reactor [PDF]
Cascade is an inertial fusion reactor that uses circulating Li/sub 2/O pellets as a coolant and tritium breeding medium. The pellets flow through a horizontal rotating vessel, and they are held against the vessel wall by centrifugal force. Three wall designs were considered: a steel shell and a SiC shell prestressed by Al or steel cables.
openaire +2 more sources
A novel Breeding Blanket (BB) concept, the Water-cooled Lead and Ceramic Breeder (WLCB) BB, has been developed under the EUROfusion Programme to address key challenges identified during the Pre-Conceptwual Design (PCD) phase for the driver BB concepts ...
Iole Palermo +6 more
doaj +1 more source
Commercial objectives, technology transfer, and systems analysis for fusion power development [PDF]
Fusion is an inexhaustible source of energy that has the potential for economic commercial applications with excellent safety and environmental characteristics.
Dean, Stephen O.
core +1 more source
Packing density of the tritium breeder pebble beds are closely related to the effective density of the lithium atom in the breeding cavities. And the higher the density of lithium atoms the higher the tritium breeding ratio.
Baoping Gong +7 more
doaj +1 more source
Uncertainty assessment methodologies applied to Tritium production in fusion lithium breeding blankets [PDF]
- Need of Tritium production - Neutronic objectives - The Frascati experiment - Measurements of Tritium ...
Cabellos de Francisco, Oscar Luis +2 more
core
Neutronics analysis of spin-polarized fuel in spherical tokamaks
The effect of spin-polarized deuterium–tritium fuel on the blanket, magnets, and surrounding structures is analyzed for a spherical tokamak fusion power plant.
Jin Whan Bae +7 more
doaj +1 more source
Optimized Water Distillation Layout for Detritiation Purpose
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
BABY 1L: First Tritium Breeding Campaign Results
Achieving tritium self-sufficiency is a critical challenge for future fusion power plants. The BABY 1L experiment, part of the LIBRA project at MIT, aims to benchmark tritium breeding and release in molten salt breeder systems under deuterium-tritium (DT) neutron irradiation.
Delaporte-Mathurin, Rémi +10 more
openaire +2 more sources
Effect of divertor on tritium breeding in HELIAS
This study presents tritium breeding calculations for the five-period helical-axis advanced stellarator (HELIAS) using the Serpent2 code. To address the absence of a detailed divertor design, a simplified divertor model with a layered homogenized structure was integrated into the parametric geometry of the HELIAS.
Tommi Lyytinen +3 more
openaire +2 more sources

