Fusion Engineering and Design

An International Journal for Fusion Energy and Technology devoted to Experiments, Theory, Methods and Design

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最新論文

Corrigendum to “Improving the Newton cooling model to drive the optimization method for heterogeneous storage of ECRH hot data” [Fusion Engineering and Design 215 (2026) 115715]
Corrigendum to “Relativistic effects on stopping power of plasmas with heavy ions” [Fusion Engineering and Design 205 (2024), 114524]
Corrigendum to “Initial accident scenario analysis in support of a preliminary DEMO tritium plant design” [Fusion Engineering and Design 189 (2023) 113482]
Thermal behaviour of ZrCo getter beds during hydrogen absorption at variable flow rates and concentrations
Performance of the W7-X ECRH gyrotron diamond output window at 2 MW operation

AI解説分析論文一覧

Fusion Engineering and Design

最新論文

Effect of heat treatment on physical properties of tungsten coating obtained by pulse electrodeposition

Deuterium inventory determination in beryllium and mixed beryllium-carbon layers doped with oxygen

Integration of the TESPEL injection system at W7-X

Performance assessment of the Helium cooled First Wall mock-up in HELOKA facility

The effect of surface oxides and grain sizes on the deuterium permeation behavior of niobium membranes

Numerical research of magnetohydrodynamics buoyant flow in dual functional lead lithium fusion blanket

Assessment of nitrogen fluence from the divertor plasma in nitrogen seeded discharges

Trace tritium removal in China reduced activation ferritic-martensitic steels through thermal desorption with/without hydrogen isotope exchange

Development of a viable route for lithium-6 supply of DEMO and future fusion power plants

Stability analysis for the voltage of EAST loads based on the short circuit capacity

Modelling of multistage plasma focus using Sing Lee’s model

Cohesion and tensile properties of W-TiC interface under irradiation

A multi-channel correlation ECE system for electron temperature fluctuation measurement on EAST tokamak

Effect of composite interlayer on bonding quality of W and steel HIP joint

Mechanical properties evaluation and plastic instabilities of Fe-9%Cr ODS steels

Numerical simulation of MHD flows in a coupled U-turn rectangular duct with different wall conductance ratios

Dimensioning of ideal membrane cascade systems for the separation of binary gas mixtures for nuclear fusion applications

Separation of lithium isotopes by using solvent extraction system of crown ether-ionic liquid

Model for a beam driven plasma neutraliser based on ITER beam geometry

IFMIF-DONES systems engineering approach

Grain boundary strengthened W-ZrB2 alloy via freeze-drying technique and spark plasma sintering

Design, mechanical analysis and manufacturing of the IFMIF LIPAc beam dump shielding

Derivation of bootstrap current fraction scaling formula for 0-D system code analysis

Probabilistic safety assessment and human reliability analysis for the Wendelstein 7-X fusion device

Emissivity measurement of tungsten plasma facing components of the WEST tokamak

Measurement of leakage neutron spectra for zirconium with D-T neutrons and validation of evaluated nuclear data

Low cycle fatigue behavior of electron beam welded joint of CLAM steel at room temperature

A comparison between GDP and PDP experiments of hydrogen permeation through 15 μm Pd60-Cu40% membrane thickness in a micro channel plate type reactor

Concept selection of the automated inspection and maintenance test unit for the EU DEMO using a novel fuzzy-based decision support tool

Tensile and impact properties of tungsten-rhenium alloy for plasma-facing components in fusion reactor

Fusion Engineering and Design

最新論文

Effect of heat treatment on physical properties of tungsten coating obtained by pulse electrodeposition

Deuterium inventory determination in beryllium and mixed beryllium-carbon layers doped with oxygen

Integration of the TESPEL injection system at W7-X

Performance assessment of the Helium cooled First Wall mock-up in HELOKA facility

The effect of surface oxides and grain sizes on the deuterium permeation behavior of niobium membranes

Numerical research of magnetohydrodynamics buoyant flow in dual functional lead lithium fusion blanket

Assessment of nitrogen fluence from the divertor plasma in nitrogen seeded discharges

Trace tritium removal in China reduced activation ferritic-martensitic steels through thermal desorption with/without hydrogen isotope exchange

Development of a viable route for lithium-6 supply of DEMO and future fusion power plants

Stability analysis for the voltage of EAST loads based on the short circuit capacity

Modelling of multistage plasma focus using Sing Lee’s model

Cohesion and tensile properties of W-TiC interface under irradiation

A multi-channel correlation ECE system for electron temperature fluctuation measurement on EAST tokamak

Effect of composite interlayer on bonding quality of W and steel HIP joint

Mechanical properties evaluation and plastic instabilities of Fe-9%Cr ODS steels

Numerical simulation of MHD flows in a coupled U-turn rectangular duct with different wall conductance ratios

Dimensioning of ideal membrane cascade systems for the separation of binary gas mixtures for nuclear fusion applications

Separation of lithium isotopes by using solvent extraction system of crown ether-ionic liquid

Model for a beam driven plasma neutraliser based on ITER beam geometry

IFMIF-DONES systems engineering approach

Grain boundary strengthened W-ZrB2 alloy via freeze-drying technique and spark plasma sintering

Design, mechanical analysis and manufacturing of the IFMIF LIPAc beam dump shielding

Derivation of bootstrap current fraction scaling formula for 0-D system code analysis

Probabilistic safety assessment and human reliability analysis for the Wendelstein 7-X fusion device

Emissivity measurement of tungsten plasma facing components of the WEST tokamak

Measurement of leakage neutron spectra for zirconium with D-T neutrons and validation of evaluated nuclear data

Low cycle fatigue behavior of electron beam welded joint of CLAM steel at room temperature

A comparison between GDP and PDP experiments of hydrogen permeation through 15 μm Pd60-Cu40% membrane thickness in a micro channel plate type reactor

Concept selection of the automated inspection and maintenance test unit for the EU DEMO using a novel fuzzy-based decision support tool

Tensile and impact properties of tungsten-rhenium alloy for plasma-facing components in fusion reactor

A comparison between GDP and PDP experiments of hydrogen permeation through 15 μm Pd60-Cu40% membrane thickness in a micro channel plate type reactor