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

Fusion Engineering and Design

最新論文

Development and qualification of functional materials for the European HCPB TBM

On the thermal and thermomechanical assessment of the “Optimized Conservative” helium-cooled lithium lead breeding blanket concept for DEMO

Beam extraction characteristics of a low-energy, high-current pulsed ion source of a versatile experiment spherical torus neutral beam injector

Completion of ENEA’s casing procurement forJT-60SA toroidal field coils

Simplified models of the ITER vacuum vessel for global seismic analyses

Shutdown dose rate measurements after the 2016 Deuterium-Deuterium campaign at JET

Dependability assessment of ITER cask & plug remote handling system during nuclear maintenance operations

Virtual Reality: Lessons learned from WEST design and perspectives for nuclear environment

Thermomechanical analysis supporting the preliminary engineering design of DONES target assembly

Tritium transport model at the minimal functional unit level for HCLL and WCLL breeding blankets of DEMO

Impact of the monoblock thickness in an ITER-like configuration of DEMO divertor

Quantification of main wall erosion/deposition pattern in n = 2 RMP KSTAR H-mode plasmas

Analysis of the optimum impurity mix for the EU DEMO scenario

Fusion DEMO reactor design based on nuclear analysis

Beam diagnostics of an ECR ion source on LIPAc injector for prototype IFMIF beam accelerator

Molten salt thermal conductivity enhancement by mixing nanoparticles

Electron temperature estimation using the Pulse Height Analysis system at Wendelstein 7-X stellarator

Study of impurity behaviour for first magnetic configuration changes in W7-X plasmas by means of PHA spectra

Maintainability of the helical reactor FFHR-c1 equipped with the liquid metal divertor and cartridge-type blankets

Effect of induction heating on flaw generation and expansion

Tritium release from molten salt FLiNaK under low flux neutron irradiation with an AmBe neutron source

Preliminary study of DEMO disruptions due to component failures

Neutronic analyses in support of the WCLL DEMO design development

The safety report of future fusion power plants

Hydrodynamic characteristics of mixed catalytic packing for heavy water detritiation

Analysis of test blanket module attachments under electromagnetic loads by using a dynamic amplification factor envelope

Effect of Resonant Magnetic Perturbation on erosion of divertor region in KSTAR

Safety classification of mechanical components for fusion application

Investigation on the “advanced-plus” Helium Cooled Lithium Lead Breeding Blanket design concept for TBR enhancement regarding thermal and mechanical behavior

Modelling an in-vessel loss of coolant accident in the EU DEMO WCLL breeding blanket with the GETTHEM code

Fusion Engineering and Design

最新論文

Fusion Engineering and Design

最新論文

Development and qualification of functional materials for the European HCPB TBM

On the thermal and thermomechanical assessment of the “Optimized Conservative” helium-cooled lithium lead breeding blanket concept for DEMO

Beam extraction characteristics of a low-energy, high-current pulsed ion source of a versatile experiment spherical torus neutral beam injector

Completion of ENEA’s casing procurement forJT-60SA toroidal field coils

Simplified models of the ITER vacuum vessel for global seismic analyses

Shutdown dose rate measurements after the 2016 Deuterium-Deuterium campaign at JET

Dependability assessment of ITER cask & plug remote handling system during nuclear maintenance operations

Virtual Reality: Lessons learned from WEST design and perspectives for nuclear environment

Thermomechanical analysis supporting the preliminary engineering design of DONES target assembly

Tritium transport model at the minimal functional unit level for HCLL and WCLL breeding blankets of DEMO

Impact of the monoblock thickness in an ITER-like configuration of DEMO divertor

Quantification of main wall erosion/deposition pattern in n = 2 RMP KSTAR H-mode plasmas

Analysis of the optimum impurity mix for the EU DEMO scenario

Fusion DEMO reactor design based on nuclear analysis

Beam diagnostics of an ECR ion source on LIPAc injector for prototype IFMIF beam accelerator

Molten salt thermal conductivity enhancement by mixing nanoparticles

Electron temperature estimation using the Pulse Height Analysis system at Wendelstein 7-X stellarator

Study of impurity behaviour for first magnetic configuration changes in W7-X plasmas by means of PHA spectra

Maintainability of the helical reactor FFHR-c1 equipped with the liquid metal divertor and cartridge-type blankets

Effect of induction heating on flaw generation and expansion

Tritium release from molten salt FLiNaK under low flux neutron irradiation with an AmBe neutron source

Preliminary study of DEMO disruptions due to component failures

Neutronic analyses in support of the WCLL DEMO design development

The safety report of future fusion power plants

Hydrodynamic characteristics of mixed catalytic packing for heavy water detritiation

Analysis of test blanket module attachments under electromagnetic loads by using a dynamic amplification factor envelope

Effect of Resonant Magnetic Perturbation on erosion of divertor region in KSTAR

Safety classification of mechanical components for fusion application

Investigation on the “advanced-plus” Helium Cooled Lithium Lead Breeding Blanket design concept for TBR enhancement regarding thermal and mechanical behavior

Modelling an in-vessel loss of coolant accident in the EU DEMO WCLL breeding blanket with the GETTHEM code

Quantification of main wall erosion/deposition pattern in n = 2 RMP KSTAR H-mode plasmas