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

A hybrid analysis procedure enabling elastic design rule assessment of monoblock-type divertor components

Aiming at understanding thermo-mechanical loads in the first wall of DEMO: Stress–strain evolution in a Eurofer-tungsten test component featuring a functionally graded interlayer

Study on rectangular-to-circular waveguide mode converter for KSTAR LHCD transmission line

Influence of low energy radiations on the fusion chamber dynamics and first wall response in a Z-Pinch driven fusion-fission hybrid reactor (Z-FFR)

Neutron transport and benchmark on granular tungsten samples with 14.8 MeV neutrons

A study regarding the optimal radial build of a low-aspect-ratio tokamak fusion system

Corrosion behavior of IN-RAFM steel with stagnant lead-lithium at 550 °C up to 9000 h

Laser induced ablation spectroscopy for in situ characterization of the first wall on EAST tokamak

Effects of Ti addition on microstructure and mechanical property of spark-plasma-sintered transformable 9Cr-ODS steels

A distillation column for hydrogen isotope removal from liquid lithium

Study of hydrogen recovery from Li-Pb using packed tower

Numerical analysis of the manufacturing processes of a mock-up of the ITER NHF First Wall Panel

Fabrication of W/steel joint using hot isostatic pressing with Ti/Cu/Ti liquid forming interlayer

Neutron shielding assessment for the Remote Handling Lower Port rack of ITER

Control-oriented model of disruption generated RE beam at FTU

Thermo-structural design of the European DEMO water-cooled blanket with a multiscale-multiphysics framework

Fabrication and characterization of W-Cu functionally graded material by spark plasma sintering process

Extrusion process of 316LN L-shape stainless steel and manufacture process of ITER side correction coil box

Development of EUROFER97 database and material property handbook

Feasibility experiment of physics-based global electron temperature profile control in KSTAR

Manufacturing progress of first delivery sector of ITER vacuum vessel thermal shield

High heat flux test and cooling effect of tungsten brazed mockups with swirl tube

Neutron/Gamma discrimination code based on trapezoidal filter

Hydrogen breakthrough behaviors for cryogenic adsorption and HAZOP study

RF design of Passive Active Multijunction (PAM) launcher for LHCD system of ADITYA-Upgrade tokamak

Comparison of X-ray and neutron tomographic imaging to qualify manufacturing of a fusion divertor tungsten monoblock

Update in the nuclear responses of the European TBMs for ITER during operation and shutdown

Sizing of a recuperative supercritical CO2 Brayton cycle as power conversion system for DEMO fusion reactor based on Dual Coolant Lithium Lead blanket

Magnetic field of heliotron with irregular helical coil pitch

Thermo-hydraulic optimization study for a high heat flux unit of the K-DEMO divertor target

Fusion Engineering and Design

最新論文

A hybrid analysis procedure enabling elastic design rule assessment of monoblock-type divertor components

Aiming at understanding thermo-mechanical loads in the first wall of DEMO: Stress–strain evolution in a Eurofer-tungsten test component featuring a functionally graded interlayer

Study on rectangular-to-circular waveguide mode converter for KSTAR LHCD transmission line

Influence of low energy radiations on the fusion chamber dynamics and first wall response in a Z-Pinch driven fusion-fission hybrid reactor (Z-FFR)

Neutron transport and benchmark on granular tungsten samples with 14.8 MeV neutrons

A study regarding the optimal radial build of a low-aspect-ratio tokamak fusion system

Corrosion behavior of IN-RAFM steel with stagnant lead-lithium at 550 °C up to 9000 h

Laser induced ablation spectroscopy for in situ characterization of the first wall on EAST tokamak

Effects of Ti addition on microstructure and mechanical property of spark-plasma-sintered transformable 9Cr-ODS steels

A distillation column for hydrogen isotope removal from liquid lithium

Study of hydrogen recovery from Li-Pb using packed tower

Numerical analysis of the manufacturing processes of a mock-up of the ITER NHF First Wall Panel

Fabrication of W/steel joint using hot isostatic pressing with Ti/Cu/Ti liquid forming interlayer

Neutron shielding assessment for the Remote Handling Lower Port rack of ITER

Control-oriented model of disruption generated RE beam at FTU

Thermo-structural design of the European DEMO water-cooled blanket with a multiscale-multiphysics framework

Fabrication and characterization of W-Cu functionally graded material by spark plasma sintering process

Extrusion process of 316LN L-shape stainless steel and manufacture process of ITER side correction coil box

Development of EUROFER97 database and material property handbook

Feasibility experiment of physics-based global electron temperature profile control in KSTAR

Manufacturing progress of first delivery sector of ITER vacuum vessel thermal shield

High heat flux test and cooling effect of tungsten brazed mockups with swirl tube

Neutron/Gamma discrimination code based on trapezoidal filter

Hydrogen breakthrough behaviors for cryogenic adsorption and HAZOP study

RF design of Passive Active Multijunction (PAM) launcher for LHCD system of ADITYA-Upgrade tokamak

Comparison of X-ray and neutron tomographic imaging to qualify manufacturing of a fusion divertor tungsten monoblock

Update in the nuclear responses of the European TBMs for ITER during operation and shutdown

Sizing of a recuperative supercritical CO2 Brayton cycle as power conversion system for DEMO fusion reactor based on Dual Coolant Lithium Lead blanket

Magnetic field of heliotron with irregular helical coil pitch

Thermo-hydraulic optimization study for a high heat flux unit of the K-DEMO divertor target

Neutron transport and benchmark on granular tungsten samples with 14.8 MeV neutrons

Corrosion behavior of IN-RAFM steel with stagnant lead-lithium at 550 °C up to 9000 h