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

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

The ITER tokamak neutronics reference model C-Model

DEMO design activity in Europe: Progress and updates

Design progress of ITER blanket remote handling system towards manufacturing

Conceptual design of HCCR-TBM diagnostics

Operational domain of Proto-MPEX

A study on influence of magnetic field on fracture properties of China low activation martensitic steel

Investigation of edge impurity transport derived from the first wall on EAST with EMC3-EIRENE modelling

Activation analysis of coolant in a water-cooled loop of China fusion engineering test reactor

Numerical simulation and experimental research on temperature and stress fields in TIG welding for plate of RAFM steel

Development of tungsten divertor components for ITER in Japan

Influence of modified neutron emission spectrum on tritium production performance in blanket systems with NBI-heated deuterium plasma

Effects of baking in deuterium atmosphere on tritium removal from tungsten

An FEM-BEM method for halo current problem and its application to HL-2M Tokamak

Design, manufacturing and installation of the JT-60SA vacuum vessel gravity support

Enhancement of cooling performance of a helium-cooled divertor through the addition of rib structures on the jet-impingement area

Thermal mechanical analyses of the mm-wave miter bend for the ITER electron cyclotron upper launcher first confinement system

Proposal for Combined Electrolysis and Catalytic Exchange System (CECE) development within the Pilot Plant

New high performance computing software for multiphysics simulations of fusion reactors

Large-scale behavior of sandwich-like FCI components within the EU-DCLL operational conditions

Overview of the current status of IFMIF-DONES test cell biological shielding design

The effect of wall flow velocity on compatibility of high-purity SiC materials with liquid Pb-Li alloy by rotating disc testing for 3000 h up to 900 °C

Activity inventories and decay heat generation of the Test Cell facility of IFMIF-DONES

Laser welding of fusion relevant steels for the European DEMO

Compatibility test of common electronics with gaseous tritium

Radiation shielding calculations for a 3D ITER benchmark model using TRIPOLI-4® Monte Carlo code

Operational characteristics of the superconducting high flux plasma generator Magnum-PSI

Study of the optimal configuration for a Gas Electron Multiplier aimed at plasma impurity radiation monitoring

Study on lithium rod test module and irradiation method for tritium production using high temperature gas-cooled reactor

Dust generation in tokamaks: Overview of beryllium and tungsten dust characterisation in JET with the ITER-like wall

MASCOT 6: Achieving high dexterity tele-manipulation with a modern architectural design for fusion remote maintenance

Fusion Engineering and Design

最新論文

Fusion Engineering and Design

最新論文

The ITER tokamak neutronics reference model C-Model

DEMO design activity in Europe: Progress and updates

Design progress of ITER blanket remote handling system towards manufacturing

Conceptual design of HCCR-TBM diagnostics

Operational domain of Proto-MPEX

A study on influence of magnetic field on fracture properties of China low activation martensitic steel

Investigation of edge impurity transport derived from the first wall on EAST with EMC3-EIRENE modelling

Activation analysis of coolant in a water-cooled loop of China fusion engineering test reactor

Numerical simulation and experimental research on temperature and stress fields in TIG welding for plate of RAFM steel

Development of tungsten divertor components for ITER in Japan

Influence of modified neutron emission spectrum on tritium production performance in blanket systems with NBI-heated deuterium plasma

Effects of baking in deuterium atmosphere on tritium removal from tungsten

An FEM-BEM method for halo current problem and its application to HL-2M Tokamak

Design, manufacturing and installation of the JT-60SA vacuum vessel gravity support

Enhancement of cooling performance of a helium-cooled divertor through the addition of rib structures on the jet-impingement area

Thermal mechanical analyses of the mm-wave miter bend for the ITER electron cyclotron upper launcher first confinement system

Proposal for Combined Electrolysis and Catalytic Exchange System (CECE) development within the Pilot Plant

New high performance computing software for multiphysics simulations of fusion reactors

Large-scale behavior of sandwich-like FCI components within the EU-DCLL operational conditions

Overview of the current status of IFMIF-DONES test cell biological shielding design

The effect of wall flow velocity on compatibility of high-purity SiC materials with liquid Pb-Li alloy by rotating disc testing for 3000 h up to 900 °C

Activity inventories and decay heat generation of the Test Cell facility of IFMIF-DONES

Laser welding of fusion relevant steels for the European DEMO

Compatibility test of common electronics with gaseous tritium

Radiation shielding calculations for a 3D ITER benchmark model using TRIPOLI-4® Monte Carlo code

Operational characteristics of the superconducting high flux plasma generator Magnum-PSI

Study of the optimal configuration for a Gas Electron Multiplier aimed at plasma impurity radiation monitoring

Study on lithium rod test module and irradiation method for tritium production using high temperature gas-cooled reactor

Dust generation in tokamaks: Overview of beryllium and tungsten dust characterisation in JET with the ITER-like wall

MASCOT 6: Achieving high dexterity tele-manipulation with a modern architectural design for fusion remote maintenance

The effect of wall flow velocity on compatibility of high-purity SiC materials with liquid Pb-Li alloy by rotating disc testing for 3000 h up to 900 °C