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

Development of intelligent control module for the J-TEXT electron cyclotron emission imaging system

Design and testing of the 40 kV/20A solid-state switch based on SiC MOSFETs for ECRH on J-TEXT Tokamak

Hydrogen isotope permeability of reduced activation ferritic/martensitic steel CLF-1 corroded by Li4SiO4

Real-time control of the deposition location of ECRH in the LHD

Research progress of HL-2M distributed timing system

Safety analysis of the 100 kA HTS current lead for CFETR

A water distillation detritiation facility and its performance test

Shielding analysis for TCP and IVVS bio-shield plugs of ITER

Construction and experimental tests of the high frequency pellet injection system on EAST tokamak

Selection of molybdenum lines by quantitative analysis of molybdenum- zirconium-titanium alloy by CF-LIBS for future fusion applications

Primary heat transfer system design of the WCCB blanket for multiple operation modes of CFETR

Non-plasma diagnostic instrumentation for a next-step tokamak with a burning plasma

Investigation of neutron source model based on EAST plasma shape

Analysis of the Ingress of Coolant Event tests performed in the upgraded ICE facility aimed at the ECART code validation

Realization of the requirements for a safe operation of Wendelstein 7-X

An efficient MHD equilibrium solver for control oriented transport models

Integrated data acquisition, storage and retrieval for glass spherical tokamak (GLAST)

Variations in mechanical properties of RAFM steel under vacuum diffusion welding with pre-deformation and subsequent heat treatment

Estimation of effective thermal conductivity of packed bed with internal heat generation

Effect of natural oxide film on the deuterium permeation behavior of 430 stainless steel

Thermal conductivity and thermal diffusivity of Li-Pb eutectic in the temperature range of 293–1273 K

A first-principles study of the mechanical and thermodynamic properties of WTi, WV, W2Zr, WVTi, WVZr alloys

NG-TIG welding technology research on 1/8 Sector of CFETR vacuum vessel

Tungsten modified by potassium doping and rhenium addition for fusion reactor applications

Ratcheting and fatigue behavior of Eurofer97 at high temperature, part 2: modeling

The voltage response test of ITER PF converter bridge

The design of software development platform for CFETR plasma control system

The development of a three-dimensional finite element method code for the heat flux analysis of tungsten monoblock divertor on EAST

Optimization design for plasma configuration at the CFETR

Microstructure and mechanical properties of thick CLF-1 reduced activation steel weld joint made by electron beam welding joint

Fusion Engineering and Design

最新論文

Fusion Engineering and Design

最新論文

Development of intelligent control module for the J-TEXT electron cyclotron emission imaging system

Design and testing of the 40 kV/20A solid-state switch based on SiC MOSFETs for ECRH on J-TEXT Tokamak

Hydrogen isotope permeability of reduced activation ferritic/martensitic steel CLF-1 corroded by Li4SiO4

Real-time control of the deposition location of ECRH in the LHD

Research progress of HL-2M distributed timing system

Safety analysis of the 100 kA HTS current lead for CFETR

A water distillation detritiation facility and its performance test

Shielding analysis for TCP and IVVS bio-shield plugs of ITER

Construction and experimental tests of the high frequency pellet injection system on EAST tokamak

Selection of molybdenum lines by quantitative analysis of molybdenum- zirconium-titanium alloy by CF-LIBS for future fusion applications

Primary heat transfer system design of the WCCB blanket for multiple operation modes of CFETR

Non-plasma diagnostic instrumentation for a next-step tokamak with a burning plasma

Investigation of neutron source model based on EAST plasma shape

Analysis of the Ingress of Coolant Event tests performed in the upgraded ICE facility aimed at the ECART code validation

Realization of the requirements for a safe operation of Wendelstein 7-X

An efficient MHD equilibrium solver for control oriented transport models

Integrated data acquisition, storage and retrieval for glass spherical tokamak (GLAST)

Variations in mechanical properties of RAFM steel under vacuum diffusion welding with pre-deformation and subsequent heat treatment

Estimation of effective thermal conductivity of packed bed with internal heat generation

Effect of natural oxide film on the deuterium permeation behavior of 430 stainless steel

Thermal conductivity and thermal diffusivity of Li-Pb eutectic in the temperature range of 293–1273 K

A first-principles study of the mechanical and thermodynamic properties of WTi, WV, W2Zr, WVTi, WVZr alloys

NG-TIG welding technology research on 1/8 Sector of CFETR vacuum vessel

Tungsten modified by potassium doping and rhenium addition for fusion reactor applications

Ratcheting and fatigue behavior of Eurofer97 at high temperature, part 2: modeling

The voltage response test of ITER PF converter bridge

The design of software development platform for CFETR plasma control system

The development of a three-dimensional finite element method code for the heat flux analysis of tungsten monoblock divertor on EAST

Optimization design for plasma configuration at the CFETR

Microstructure and mechanical properties of thick CLF-1 reduced activation steel weld joint made by electron beam welding joint

Design and testing of the 40 kV/20A solid-state switch based on SiC MOSFETs for ECRH on J-TEXT Tokamak

Thermal conductivity and thermal diffusivity of Li-Pb eutectic in the temperature range of 293–1273 K