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

First-principles study of the diffusion of Li in bcc Fe

Effects of gaseous media on interfacial microstructure and mechanical properties of titanium/steel explosive welded composite plate

Effect of simulated stress-relieving heat treatment on microstructure and tensile properties of CLAM steel

Geometrical effect in the measurement of the CXRS on EAST

Development of the quasi-optical combiner systems for density profile reflectometers on the EAST tokamak

Effect of welding techniques on the microstructure and mechanical properties of reduced activation ferritic-martensitic (RAFM) steel weld joints

Measurement of n = 1 locked mode using locked mode coils in KSTAR

Low energy deuterium plasma driven permeation through tungsten

Calibration of the gamma-ray measurement procedure in the EAST neutron activation system

Investigation of the correlation between the electrical contact resistance and the contact area of mechanical lap joint fabricated with high-temperature superconducting tapes using X-ray microtomography

Assessment of electromagnetic loads for EAST plasma facing components using integral parameters method

Upgrade of poloidal field coils current measurement system on Experimental Advanced Superconducting Tokamak

The data acquisition and control system for the operation of ASDEX pressure gauge for the measurement of neutral pressure in ADITYA Tokamak

Assessment of n = 1 “overlap” error field produced by localized steel objects placed at different levels of ITER Tokamak building

Effects of activation products on tritium measurements for tungsten in fusion reactors

Preliminary results of CuCrZr/316L tube-to-tube junctions fabricated with rotary friction welding

Automated mode recovery for gyrotrons demonstrated at Wendelstein 7-X

Effects of structural and concentration polarization on the efficiency of Pd membrane permeator

Leak tight joint procedures for ODS-Cu/ODS-Cu by the advanced brazing technique

Design of tomographic diagnostic system for Indian Test Facility (INTF) neutral beam injector

Corrigendum to “Development of the material property handbook and database of CuCrZr” [Fusion Eng. Des. 144 (July) (2019) 148–153]

Welding technology development for the fabrication of vacuum vessel for CFETR

Conceptual design of a high heat flux testing facility in support of CFETR

First plasma scenario development for HL-2M

Optimization of W/Cu monoblock mock-up with FGM interlayer for CFETR devertor targets

Systems engineering activities supporting the heating & current drive and fuelling lines systems integration in the European DEMO breeding blanket

Tokamak-agnostic actuator management for multi-task integrated control with application to TCV and ITER

Development of a 1D thermofluid code for divertor target plate modeling

Challenges and status of the ITER IVC conductor qualification process in China

Phase transformations in reduced-activation duplex alloy Fe52Mn30Cr18 under isothermal heat treatment

Fusion Engineering and Design

最新論文

Fusion Engineering and Design

最新論文

First-principles study of the diffusion of Li in bcc Fe

Effects of gaseous media on interfacial microstructure and mechanical properties of titanium/steel explosive welded composite plate

Effect of simulated stress-relieving heat treatment on microstructure and tensile properties of CLAM steel

Geometrical effect in the measurement of the CXRS on EAST

Development of the quasi-optical combiner systems for density profile reflectometers on the EAST tokamak

Effect of welding techniques on the microstructure and mechanical properties of reduced activation ferritic-martensitic (RAFM) steel weld joints

Measurement of n = 1 locked mode using locked mode coils in KSTAR

Low energy deuterium plasma driven permeation through tungsten

Calibration of the gamma-ray measurement procedure in the EAST neutron activation system

Investigation of the correlation between the electrical contact resistance and the contact area of mechanical lap joint fabricated with high-temperature superconducting tapes using X-ray microtomography

Assessment of electromagnetic loads for EAST plasma facing components using integral parameters method

Upgrade of poloidal field coils current measurement system on Experimental Advanced Superconducting Tokamak

The data acquisition and control system for the operation of ASDEX pressure gauge for the measurement of neutral pressure in ADITYA Tokamak

Assessment of n = 1 “overlap” error field produced by localized steel objects placed at different levels of ITER Tokamak building

Effects of activation products on tritium measurements for tungsten in fusion reactors

Preliminary results of CuCrZr/316L tube-to-tube junctions fabricated with rotary friction welding

Automated mode recovery for gyrotrons demonstrated at Wendelstein 7-X

Effects of structural and concentration polarization on the efficiency of Pd membrane permeator

Leak tight joint procedures for ODS-Cu/ODS-Cu by the advanced brazing technique

Design of tomographic diagnostic system for Indian Test Facility (INTF) neutral beam injector

Corrigendum to “Development of the material property handbook and database of CuCrZr” [Fusion Eng. Des. 144 (July) (2019) 148–153]

Welding technology development for the fabrication of vacuum vessel for CFETR

Conceptual design of a high heat flux testing facility in support of CFETR

First plasma scenario development for HL-2M

Optimization of W/Cu monoblock mock-up with FGM interlayer for CFETR devertor targets

Systems engineering activities supporting the heating & current drive and fuelling lines systems integration in the European DEMO breeding blanket

Tokamak-agnostic actuator management for multi-task integrated control with application to TCV and ITER

Development of a 1D thermofluid code for divertor target plate modeling

Challenges and status of the ITER IVC conductor qualification process in China

Phase transformations in reduced-activation duplex alloy Fe52Mn30Cr18 under isothermal heat treatment

Measurement of n = 1 locked mode using locked mode coils in KSTAR

Assessment of n = 1 “overlap” error field produced by localized steel objects placed at different levels of ITER Tokamak building