Results 41 to 50 of about 79,921 (199)

Preliminary evaluation of the expansion system size for a pressurized gas loop: Application to a fusion reactor based on a helium-cooled blanket [PDF]

open access: yes, 2017
Some considerations to preliminarily design the size of the Expansion Volume (EV) and the relief pipes for a Vacuum Vessel Pressure Suppression System, to be adopted in a fusion reactor based on a helium cooled blanket, are presented.
CARUSO, Gianfranco, NOBILI, MATTEO
core   +1 more source

IFMIF suitability for evaluation of fusion functional materials [PDF]

open access: yes, 2011
The International FusionMaterials Irradiation Facility (IFMIF) is a future neutron source based on the D-Li stripping reaction, planned to test candidate fusionmaterials at relevant fusion irradiation conditions.
A. GarcĂ­a   +25 more
core   +2 more sources

A Review of Fusion and Tokamak Research Towards Steady-State Operation: A JAEA Contribution

open access: yesEnergies, 2010
Providing a historical overview of 50 years of fusion research, a review of the fundamentals and concepts of fusion and research efforts towards the implementation of a steady state tokamak reactor is presented.
Mitsuru Kikuchi
doaj   +1 more source

Measurement and Verification of Trace Components in Neon by Gas Chromatography

open access: yesHe huaxue yu fangshe huaxue, 2022
In order to complete the tritium production of irradiated tritium breeder in the solid tritium breeder reactor of fusion reactor, in addition to the conventional ionization chamber, a high-precision gas chromatography on-line detection and analysis ...
YANG Li-ling, ZHAN Qin, YANG Hong-guang
doaj   +1 more source

Preliminary Design of the Electrical Power Systems for DTT Nuclear Fusion Plant

open access: yesApplied Sciences, 2021
The realization of the Divertor Tokamak Test (DTT) facility is one of the key milestones of the European Roadmap, aiming to explore alternative power exhaust solutions for DEMO, the first nuclear-fusion power plant that will be connected to the European ...
Marzia Caldora   +3 more
doaj   +1 more source

A Two-Way Neutronics/Thermal-Hydraulics Coupling Analysis Method for Fusion Blankets and Its Application to CFETR

open access: yesEnergies, 2020
The China Fusion Engineering Test Reactor (CFETR) is a tokamak device to validate and demonstrate fusion engineering technology. In CFETR, the breeding blanket is a vital important component that is closely related to the performance and safety of the ...
Tao Dai   +4 more
doaj   +1 more source

High-resolution rapid calculation method of neutron spectrum based on energy response

open access: yesNuclear Engineering and Technology
Conventional neutron spectrum calculation methods are difficult to achieve both high resolution and high efficiency. This paper presents a high-resolution rapid calculation method of neutron spectrum.
Dongyuan Li, Qingquan Pan, Xiaojing Liu
doaj   +1 more source

Heat Transfer Potential of Unidirectional Porous Tubes for Gas Cooling under High Heat Flux Conditions

open access: yesEnergies, 2022
To discuss a suitable porous structure for helium gas cooling under high heat flux conditions of a nuclear fusion divertor, we first evaluate effective thermal conductivity of sintered copper-particles in a simple cubic lattice by direct numerical heat ...
Kazuhisa Yuki   +5 more
doaj   +1 more source

On the thermal dynamic behaviour of the helium-cooled DEMO fusion reactor [PDF]

open access: yes, 2019
The EU-DEMO conceptual design is being conducted among research institutions and universities from 26 countries of European Union, Switzerland and Ukraine. Its mission is to realise electricity from nuclear fusion reaction by 2050.
Barucca L.   +3 more
core   +1 more source

Intergranular blistering in tungsten: a survey of grain-boundary-freedom dependence using tungsten with inclined microstructure

open access: yesNuclear Fusion
The dependence of hydrogen-induced intergranular blistering on the grain boundary (GB) was investigated in chemical vapor deposition tungsten (CVD-W). Three specific inclined CVD-W samples were prepared by cutting across the surface at specific angles ...
Hao Yin   +13 more
doaj   +1 more source

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