Analysis of Coolant Purification Strategies for Tritium Control in DEMO Water Primary Coolant
Energies, 2023 A major objective of the European fusion program is the design of the DEMOnstration power plant named DEMO. Up to now, most fusion experiments have been dedicated to a plasma physics investigation while, in DEMO-oriented activities, large attention is ...
Vincenzo Narcisi +3 more
doaj +1 more source
Energies, 2023 Significant design efforts were undertaken during the Pre-Concept Design (PCD) phase of the European DEMO program to optimize the helium cooled pebble bed (HCPB) breeding blanket.
Guangming Zhou +6 more
doaj +1 more source
EFFECT OF IRRADIATION AND DEUTERIUM BEHAVIOR IN LI-BASED TRITIUM BREEDING CERAMICS
Problems of Atomic Science and Technology, 2022 The behavior of implanted deuterium in advanced lithium orthosilicate (Li4SiO4) pellets with addition of lithium metatitanate (Li2TiO3), and in reference Li4SiO4 pellets, has been investigated.
S. Karpov +3 more
semanticscholar +1 more source
Neutronic analysis of effects of inboard materials on the size of a tokamak fusion reactor
Nuclear Materials and Energy, 2021 The effects of inboard materials on the size of a tokamak fusion reactor were studied based on reactor system parameters determined through a coupled analysis of tokamak systems and neutron transport. With an inboard blanket, the shielding capability was
B.G. Hong, W. Cho
doaj +1 more source
Conceptual design of the EU-DEMO dual coolant lithium lead equatorial module [PDF]
, 2016 © 20xx IEEE. Personal use of this material is permitted. Permission from IEEE must be obtained for all other uses, in any current or future media, including reprinting/republishing this material for advertising or promotional purposes, creating new ...
Fernández, I. +6 more
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Modeling and analysis of the tritium fuel cycle for ARC- and STEP-class D-T fusion power plants
Nuclear Fusion, 2023 The limited tritium resources available for the first fusion power plants (FPPs) make fuel self-sufficiency and tritium inventory minimization leading issues in FPP design. This work builds on the model proposed by Abdou et al (2020 Nucl.
Samuele Meschini +3 more
doaj +1 more source
Neutronic Activity for Development of the Promising Alternative Water-Cooled DEMO Concepts
Applied Sciences, 2023 An emerging breeding blanket that fulfills performance criteria, meets the safety requirements, and is reliable enough to meet the plant availability is a challenging issue that assumes complex studies involving numerous neutronic analyses based on the ...
Pavel Pereslavtsev +3 more
doaj +1 more source
The Thorium Molten Salt Reactor : Moving on from the MSBR [PDF]
, 2005 A re-evaluation of the Molten Salt Breeder Reactor concept has revealed problems related to its safety and to the complexity of the reprocessing considered.
A. Nuttin +14 more
core +3 more sources
TRITIUM BREEDING AND DIRECT ENERGY CONVERSION. [PDF]
, 1972 Tritium breeding and direct energy conversion are key technological problems in the development of practical fusion reactors. Lithium in some form is needed for tritium generation, but certain chemical problems must be overcome. Alternatives to lithium metal should be considered.
openaire +3 more sources
Parametric thermal analysis for the optimization of Double Walled Tubes layout in the Water Cooled Lithium Lead inboard blanket of DEMO fusion reactor [PDF]
, 2019 Within the roadmap that will lead to the nuclear fusion exploitation for electric energy generation, the construction of a DEMOnstration (DEMO) reactor is, probably, the most important milestone to be reached since it will demonstrate the technological ...
Arena P. +4 more
core +1 more source