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

MHD pressure drop estimate for the WCLL in-magnet PbLi loop

Gamma-ray irradiation effects on optical coatings and polarizers for edge Thomson scattering system in ITER

Fuel flow and stock during deuterium-deuterium start-up of fusion reactor with advanced plasma model

A total neutron yield constraint implemented to the RNC emissivity reconstruction on ITER tokamak

Organizing Wendelstein 7-X device operation

Bare and limiter DEMO single module segment concept first Wall misalignment study by 3D field line tracing

Interaction between surface behavior and inner flow pattern of liquid Li jet for fusion neutron sources

Long-term corrosion behavior of EUROFER RAFM steel in static liquid Pb-16Li at 550 °C

Analysis of water activation in fusion and fission nuclear facilities

Evaluation of fatigue properties of reduced activation ferritic/martensitic steel, F82H for development of design criteria

Nuclear analysis of the Water cooled lithium lead DEMO reactor

Diffusion bonding experiments of 316L steels in a Gleeble 3800 thermomechanical simulator for investigation of non-destructive inspection methods

Design of the RFX-mod2 first wall

A database for developing machine learning based disruption predictors

The implementation and operation of the 4th version of KSTAR fast interlock system

From tore Supra to WEST: Evolution of the CODAC infrastructure

W7-X logbook REST API for processing experimental metadata and data enrichment at the Wendelstein 7-X stellarator

Low-risk beginning of the density control on the KSTAR plasmas

Cost-benefit analysis of condition monitoring on DEMO remote maintenance system

`ITER Equatorial Port #12 Assembly-System design, development, testing and assurance

Preliminary design and analysis of the CFQS supporting structure

Numerical simulations of MHD flows in a conduit that contracts in the magnetic field direction

Dynamic behavior and control strategy of cryogenic distillation column for hydrogen isotope separation in CFETR

An overview of the numerical methods for tokamak plasma equilibrium computation implemented in the NICE code

Influence of the material anisotropy in the estimation of the yield strength with the Small Punch Test

Plasma potential and fluctuations measurements by HIBD with 90° cylindrical energy analyzer on the ISTTOK tokamak

Real-time plasma position reflectometry system development and integration on COMPASS tokamak

Neutronic comparison of liquid breeders for ARC-like reactor blankets

Radiation damage of tungsten surface irradiated with high-energy hydrogen and helium beams of plasma focus device

Deposition of Tungsten – Tantalum composite coating on RAFM steel by sputtering deposition process

Fusion Engineering and Design

最新論文

Fusion Engineering and Design

最新論文

MHD pressure drop estimate for the WCLL in-magnet PbLi loop

Gamma-ray irradiation effects on optical coatings and polarizers for edge Thomson scattering system in ITER

Fuel flow and stock during deuterium-deuterium start-up of fusion reactor with advanced plasma model

A total neutron yield constraint implemented to the RNC emissivity reconstruction on ITER tokamak

Organizing Wendelstein 7-X device operation

Bare and limiter DEMO single module segment concept first Wall misalignment study by 3D field line tracing

Interaction between surface behavior and inner flow pattern of liquid Li jet for fusion neutron sources

Long-term corrosion behavior of EUROFER RAFM steel in static liquid Pb-16Li at 550 °C

Analysis of water activation in fusion and fission nuclear facilities

Evaluation of fatigue properties of reduced activation ferritic/martensitic steel, F82H for development of design criteria

Nuclear analysis of the Water cooled lithium lead DEMO reactor

Diffusion bonding experiments of 316L steels in a Gleeble 3800 thermomechanical simulator for investigation of non-destructive inspection methods

Design of the RFX-mod2 first wall

A database for developing machine learning based disruption predictors

The implementation and operation of the 4th version of KSTAR fast interlock system

From tore Supra to WEST: Evolution of the CODAC infrastructure

W7-X logbook REST API for processing experimental metadata and data enrichment at the Wendelstein 7-X stellarator

Low-risk beginning of the density control on the KSTAR plasmas

Cost-benefit analysis of condition monitoring on DEMO remote maintenance system

`ITER Equatorial Port #12 Assembly-System design, development, testing and assurance

Preliminary design and analysis of the CFQS supporting structure

Numerical simulations of MHD flows in a conduit that contracts in the magnetic field direction

Dynamic behavior and control strategy of cryogenic distillation column for hydrogen isotope separation in CFETR

An overview of the numerical methods for tokamak plasma equilibrium computation implemented in the NICE code

Influence of the material anisotropy in the estimation of the yield strength with the Small Punch Test

Plasma potential and fluctuations measurements by HIBD with 90° cylindrical energy analyzer on the ISTTOK tokamak

Real-time plasma position reflectometry system development and integration on COMPASS tokamak

Neutronic comparison of liquid breeders for ARC-like reactor blankets

Radiation damage of tungsten surface irradiated with high-energy hydrogen and helium beams of plasma focus device

Deposition of Tungsten – Tantalum composite coating on RAFM steel by sputtering deposition process

Long-term corrosion behavior of EUROFER RAFM steel in static liquid Pb-16Li at 550 °C