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

Ionizing radiation monitoring requirements at the Divertor Tokamak Test facility

Design and manufacturing of bulk tungsten tiles for WEST outer limiter

Dynamic modelling of the helium-cooled DEMO fusion power plant with an auxiliary boiler in Apros

Parametric study of S-CO2 cycles for the DEMO fusion reactor

Testing and analysis of steady-state helicon plasma source for the Material Plasma Exposure eXperiment (MPEX)

Fusion technologies development at ENEA Brasimone Research Centre: Status and perspectives

Assessment of DEMO WCLL breeding blanket primary heat transfer system isolation valve absorbed doses due to activated water

Magneto-convective effect on tritium transport at breeder unit level for the WCLL breeding blanket of DEMO

Measurement of delayed neutron emission from water activated by 14 MeV neutrons in a FW mock-up of ITER

Design of the European DEMO vacuum vessel inboard wall

Initial operation results of exhaust detritiation system using a polymer membrane

Evaluation of shielding efficiency of using boric acid as coolant in CFETR vacuum vessel

The flow instability phenomenon in the loss of coolant accident of the water cooled blanket

Design and preliminary analyses of the new Water Cooled Lithium Lead TBM for ITER

Emissivity measurement of PbLi droplets in a vacuum for heat recovery by radiation

Manufacturing and welding assembly of the vacuum vessel on JT-60SA

Ultrasonic test results before and after high heat flux testing on W-monoblock mock-ups of EU-DEMO vertical target

Backwards extrapolation activation diagnostics and their dynamic range for pulsed neutron source measurements

Corrosion tests of multi-layer ceramic coatings in liquid lithium-lead

Electromagnetic coupling phenomena in co-axial rectangular channels

Progress on the manufacturing of ITER thermal shields

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

Fusion Engineering and Design

最新論文

Fusion Engineering and Design

最新論文

Ionizing radiation monitoring requirements at the Divertor Tokamak Test facility

Design and manufacturing of bulk tungsten tiles for WEST outer limiter

Dynamic modelling of the helium-cooled DEMO fusion power plant with an auxiliary boiler in Apros

Parametric study of S-CO2 cycles for the DEMO fusion reactor

Testing and analysis of steady-state helicon plasma source for the Material Plasma Exposure eXperiment (MPEX)

Fusion technologies development at ENEA Brasimone Research Centre: Status and perspectives

Assessment of DEMO WCLL breeding blanket primary heat transfer system isolation valve absorbed doses due to activated water

Magneto-convective effect on tritium transport at breeder unit level for the WCLL breeding blanket of DEMO

Measurement of delayed neutron emission from water activated by 14 MeV neutrons in a FW mock-up of ITER

Design of the European DEMO vacuum vessel inboard wall

Initial operation results of exhaust detritiation system using a polymer membrane

Evaluation of shielding efficiency of using boric acid as coolant in CFETR vacuum vessel

The flow instability phenomenon in the loss of coolant accident of the water cooled blanket

Design and preliminary analyses of the new Water Cooled Lithium Lead TBM for ITER

Emissivity measurement of PbLi droplets in a vacuum for heat recovery by radiation

Manufacturing and welding assembly of the vacuum vessel on JT-60SA

Ultrasonic test results before and after high heat flux testing on W-monoblock mock-ups of EU-DEMO vertical target

Backwards extrapolation activation diagnostics and their dynamic range for pulsed neutron source measurements

Corrosion tests of multi-layer ceramic coatings in liquid lithium-lead

Electromagnetic coupling phenomena in co-axial rectangular channels

Progress on the manufacturing of ITER thermal shields

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

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