Results 31 to 40 of about 42,458 (304)

Neutronic analysis of effects of inboard materials on the size of a tokamak fusion reactor

open access: yesNuclear 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

Applicability Analysis of Energy Storage Techniques for CFETR Fusion Power Plant

open access: yes南方能源建设, 2022
[Introduction] The power output of China Fusion Engineering Test Reactor (CFETR) is periodic, which can not directly meet the stable and continuous input requirements of conventional power generation equipment. CFETR fusion power plant needs to integrate
Zhanpeng LIANG   +3 more
doaj   +1 more source

Conceptual design of the EU-DEMO dual coolant lithium lead equatorial module [PDF]

open access: yes, 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

Development of a Test Bed to Investigate Wetting Behaviours of High-Temperature Heavy Liquid Metals for Advanced Nuclear Applications

open access: yesLiquids
Specifically engineered heavy liquid metals are proposed as candidate coolants and tritium breeders for advanced nuclear applications. Understanding the wetting behaviours of these liquids on relevant substrate configurations is crucial to tackle the ...
Abhishek Saraswat   +3 more
doaj   +1 more source

Molecular Dynamics Simulations of Lead and Lithium in Liquid Phase [PDF]

open access: yes, 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

Blanket materials for dt fusion reactors [PDF]

open access: yesJournal of Nuclear Materials, 1981
Abstract This paper presents an overview of the critical materials issues that must be considered in the development of a tritium breeding blanket for a tokamak fusion reactor that operates on the D-T-Li fuel cycle. The primary requirements of the blanket system are identified and the important criteria that must be considered in the development of ...
openaire   +1 more source

The investigation of the neutronic responses of components in the K-DEMO

open access: yesNuclear Fusion, 2023
The neutronic response of consisting materials of the Korean fusion DEMOnstration reactor (K-DEMO) in its fusion neutron environment is a crucial consideration factor from the conceptual design stage of the K-DEMO.
Byung Chul Kim
doaj   +1 more source

TBM/MTM for HTS-FNSF: An Innovative Testing Strategy to Qualify/Validate Fusion Technologies for U.S. DEMO

open access: yesEnergies, 2016
The qualification and validation of nuclear technologies are daunting tasks for fusion demonstration (DEMO) and power plants. This is particularly true for advanced designs that involve harsh radiation environment with 14 MeV neutrons and high ...
Laila El-Guebaly   +3 more
doaj   +1 more source

FIRST WALL FUSION BLANKET HEAT TRANSFER [PDF]

open access: yesProceeding of International Heat Transfer Conference 7, 1982
To accommodate the high heat flux and neutron and gamma heat generation in the first wall of a fusion reactor, an array of tubes or tube-bank forms a first wall shield of the blanket. A series solution to the two-dimensional (in r,theta coordinates), time-dependent heat conduction equation has been found in terms of Fourier-Bessel (modified Bessel ...
openaire   +1 more source

Hybrid reactors: nuclear breeding or energy production? [PDF]

open access: yes, 2010
After reviewing the long-standing tradition on hybrid research, an assessment model is presented in order to characterize the hybrid performance under different objectives. In hybrids, neutron multiplication in the subcritical blanket plays a major role,
Abánades Velasco, Alberto   +3 more
core   +1 more source

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