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

Corrigendum to “Improving the Newton cooling model to drive the optimization method for heterogeneous storage of ECRH hot data” [Fusion Engineering and Design 215 (2026) 115715]
Corrigendum to “Relativistic effects on stopping power of plasmas with heavy ions” [Fusion Engineering and Design 205 (2024), 114524]
Corrigendum to “Initial accident scenario analysis in support of a preliminary DEMO tritium plant design” [Fusion Engineering and Design 189 (2023) 113482]
Thermal behaviour of ZrCo getter beds during hydrogen absorption at variable flow rates and concentrations
Performance of the W7-X ECRH gyrotron diamond output window at 2 MW operation

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

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

Latest achievements of the negative ion beam test facility ELISE

Definition of the Q-PETE experiment for investigation of hydrogen isotopes permeation through the metal structures of a DEMO HCPB breeder zone

FEM and thermal fatigue testing comparison of ITER-like divertor PFUs mock-ups for DEMO

3D modelling of tungsten fuzz growth under the bombardment of helium plasma

Inspection of delamination defect in first wall with a flexible EMAT-scanning system

Retention and permeation properties of deuterium in tungsten under irradiation of the D–He mixture plasma

Safety provisions for the ITER facility

Initial layout of DEMO buildings and configuration of the main plant systems

Overview of manufacturing technologies under development in Russia for ITER plasma facing components

Fusion Engineering and Design

最新論文

Fusion Engineering and Design

最新論文

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

Latest achievements of the negative ion beam test facility ELISE

Definition of the Q-PETE experiment for investigation of hydrogen isotopes permeation through the metal structures of a DEMO HCPB breeder zone

FEM and thermal fatigue testing comparison of ITER-like divertor PFUs mock-ups for DEMO

3D modelling of tungsten fuzz growth under the bombardment of helium plasma

Inspection of delamination defect in first wall with a flexible EMAT-scanning system

Retention and permeation properties of deuterium in tungsten under irradiation of the D–He mixture plasma

Safety provisions for the ITER facility

Initial layout of DEMO buildings and configuration of the main plant systems

Overview of manufacturing technologies under development in Russia for ITER plasma facing components

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