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

Planar coil design for the Helios stellarator fusion power plant
Equilibrium optimization of the Helios planar coil stellarator power plant
Core profile prediction and transport analysis of the Helios stellarator fusion power plant
Superconducting planar coils for magnetic field shaping in the Helios Stellarator
Design of the superconducting encircling coils for Helios, the planar coil stellarator

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Fusion Engineering and Design

最新論文

Fusion Engineering and Design

最新論文

Status of the EU DEMO HCLL breeding blanket design development

Equivalent circuit model of a rectangular RF driven hydrogen ion source for impedance matching network design

Erosion-corrosion resistance of Reduced Activation Ferritic-Martensitic steels exposed to flowing liquid Lithium

The European ITER Test Blanket Modules: Fabrication R&D progress for HCLL and HCPB

Shutdown dose rate calculation along the ITER IVVS port

The design and application of Alfvén antennas in J-TEXT tokamak

Hydrogen recovery from metal particle dispersed salt by selective microwave heating

Preparation for commissioning of materials detritiation facility at Culham Science Centre

Performance test of radiation detectors developed for ITER-TBM

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

Fusion Engineering and Design

最新論文

Fusion Engineering and Design

最新論文

Status of the EU DEMO HCLL breeding blanket design development

Equivalent circuit model of a rectangular RF driven hydrogen ion source for impedance matching network design

Erosion-corrosion resistance of Reduced Activation Ferritic-Martensitic steels exposed to flowing liquid Lithium

The European ITER Test Blanket Modules: Fabrication R&D progress for HCLL and HCPB

Shutdown dose rate calculation along the ITER IVVS port

The design and application of Alfvén antennas in J-TEXT tokamak

Hydrogen recovery from metal particle dispersed salt by selective microwave heating

Preparation for commissioning of materials detritiation facility at Culham Science Centre

Performance test of radiation detectors developed for ITER-TBM

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

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