The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.
该杂志接受关于实验（等离子体和技术）、理论、模型、方法和设计的论文，涉及磁和惯性聚变能的技术、工程和应用科学方面。感兴趣的具体领域包括：实验和反应堆的MFE和IFE设计研究聚变核技术和材料，包括覆盖层和防护层;反应堆等离子体分析;等离子加热、加燃料和真空系统;用于综合实地演练、控制和诊断的驱动器、目标和特殊技术;燃料循环分析和氚的后处理和处理;反应堆的操作和远程维护;安全、退役和废物管理;组件和系统的经济和环境分析。
DEMO tritium fuel cycle: performance, parameter explorations, and design space constraints
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.01.150
Correlation between microstructure evolution and mechanical properties of 50 mm 316L electron beam welds
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.111245
Design and preliminary operation of a laser absorption diagnostic for the SPIDER RF source
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.04.092
Calibration of the gamma-ray measurement procedure in the EAST neutron activation system
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.111278
Study on anisotropy in microstructure and tensile properties of the 12Cr oxide dispersion strengthened (ODS) steel
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.02.011
Sintering and irradiation of copper-based high entropy alloys for nuclear fusion
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.03.044
Equilibrium evaluation for Wendelstein 7-X experiment programs in the first divertor phase
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2018.12.050
Preparation for a neutronics experiment using a discharge fusion device and an imaging plate neutron detector
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.03.005
Effect of W-coated diamond on the microstructure and thermal conductivity of diamond/W matrix composites for plasma-facing materials (PFMs)
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.05.005
Application of 3D View Factor method for heat fluxes deposition on ITER Cryostat Thermal Shield
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2018.11.035
A revised and expanded liquid metal property library for MELCOR
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.04.032
Design of model tokamak particles for future toxicity studies: Morphology and physical characterization
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.05.037
Fabrication and mechanical properties of an oxide-dispersion-strengthened FeCrAl alloy
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.01.001
Tritium and dust source term inventory evaluation issues in the European DEMO reactor concepts
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.01.008
Michelson Interferometer design in ECW heated plasmas and initial results
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.01.124
Thermal and microstructural properties of spark plasma sintered tungsten for the application to plasma facing materials
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.04.071
Effect of annealing on the microstructure behavior of D+-irradiated W-2vol.%TiC composite prepared by wet-chemical method
来源期刊：Fusion Engineering and DesignDOI：10.1016/j.fusengdes.2019.111321
Thermal Loads and Cooling Design for ITER in-Port Low Field Side Reflectometer Diagnostic System
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.02.062
The anode power supply based on the pulse step modulation technology for the ECRH system on J-TEXT tokamak
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.04.072
From manufacture to assembly of the ITER central solenoid
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2018.12.086
Deuterium retention on the tungsten-coated divertor tiles of JET ITER-like wall in 2015–2016 campaign
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.03.081
Characterization of JET neutron field in irradiation locations for DD, DT and TT plasmas
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.03.078
Numerical analysis of loss of vacuum accident (LOVA) and preliminary discussion about dust resuspension for CFETR
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.03.159
TRANSP-based optimization towards tokamak scenario development
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.01.019
Galet – Benchmark of a Geant4 based application for the simulation and design of Beta Induced X-ray Spectrometry systems
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.03.086
Conceptual design of a neutral beam heating & current drive system for DTT
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2018.12.087
X-ray imaging diagnostic in the high heat flux test facilities
来源期刊：Fusion Engineering and DesignDOI：10.1016/j.fusengdes.2019.111296
F4E load transfer procedure among finite element models different in topology or in discretization
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.01.104
Validation of 500-kW/1000-s operation of 5-GHz klystron for KSTAR LHCD system
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.01.024
Multi-model quantification of defects in irradiated lithium titanate
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.02.006
Design and measuring performance of the ITER plasma position reflectometer in-port-plug antennas
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.01.078
Fabrication and characterization of Be12V pebbles with different diameters
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.01.048
Enhanced tritium production in fusion-fission hybrids for the external consumption
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.02.130
ITER magnet power conversion building construction and AC/DC converter installation
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.03.058
Laser transfer technique using wavefront correction and beam homogenizers in Thomson scattering diagnostics
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.03.014
Automation and interlock system design for Pb-Li liquid-metal purification experimental facility
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.02.094
Investigating different methods for calculating the lambda equilibrium parameter for the plasma column in the Damavand tokamak
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.02.091
Post-test examination of a Li-Ta heat pipe exposed to H plasma in Magnum PSI
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.04.053
Optimization and adjustment of impact set-up for testing of insulated pads of ITER blanket module connectors and first wall
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.04.022
Towards reliable design-by-analysis for divertor plasma facing components – Guidelines for inelastic assessment (part 1: Unirradiated)
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.06.007
Structural assessment of HL-2M in-vessel cryopump under EM loads
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.03.134
Development of a 1D thermofluid code for divertor target plate modeling
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.06.010
Upgraded gamma-ray diagnostics for DT campaigns at JET
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.01.144
Design and analysis of a high power supply for the research system of superconducting magnets
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.111248
Possibility study of the partial neutron calibration for neutron flux monitors in torus devices
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2018.11.026
Progress of KSTAR pellet injection system
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.04.010
Disruption simulations for JT-60SA design and construction
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.05.011
Thermal mixing enhancement of liquid metal film-flow by various obstacles under vertical magnetic field
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.03.128
A two colour interferometer for PROTO-SPHERA experiment
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.03.038
Interference fit process development for the ITER Vacuum Vessel Gravity Support mock-up fabrication
来源期刊：Fusion Engineering and DesignDOI：10.1016/J.FUSENGDES.2019.03.063
