Results 21 to 30 of about 7,951 (222)
Molecular Dynamics Simulations of Lead and Lithium in Liquid Phase [PDF]
, 2011 Pb17Li is today a reference breeder material in diverse fusion R&D programs worldwide. Extracting dynamic and structural properties of liquid LiPb mixtures via molecular dynamics simulations, represent a crucial step for multiscale modeling efforts ...
Cuesta Lopez, Santiago +2 more
core +3 more sources
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
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
core +3 more sources
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
Annihilation kinetics of irradiation defects in promising tritium breeding pebbles
Nuclear Materials and Energy, 2021 Lithium-based tritium breeding materials will be adopted to produce tritium in the D-T fusion reactor. Li2TiO3 and Li4SiO4 pebbles have been proposed as candidates in water-cooled ceramic breeder blanket (WCCB) and helium-cooled ceramic breeder blanket ...
Baolong. Ji +6 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
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
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