Fusion Engineering and Design

Papers
(The median citation count of Fusion Engineering and Design is 2. The table below lists those papers that are above that threshold based on CrossRef citation counts [max. 250 papers]. The publications cover those that have been published in the past four years, i.e., from 2021-08-01 to 2025-08-01.)
ArticleCitations
Steady-state Superconducting Advanced Spherical Tokamak Reactor (SASTR)102
Soft X-ray tomography using the optimized regularization method in Alvand Tokamak75
Upgrade of the cathode HVPS system for 4.6 GHz LHCD on EAST using high speed PSM72
The wide-angle infrared diagnostic for the first wall monitoring of the WEST tokamak61
Numerical calculations on liquid-metal magnetohydrodynamic flow in rectangular channel with wavelike uneven walls52
Editorial Board51
Editorial Board49
Mechanical and electrical performance of glass fiber reinforced plastic insulation for cryogenic application in fusion magnet irradiated in fast breeder reactor46
Mode purity evaluation of high-power millimeter wave transmission line by 3-port directional coupler43
Investigation of heat treatment to remove carbon on alumino-silicate fiber and mechanical and insulation properties of alumino-silicate fiber composites used at Bi-2212 CICC42
Editorial Board41
Design and engineering challenges of a multi-energy hard x-ray camera for long-pulse profile measurements at WEST tokamak41
Updating the build, test, and deploy systems for MDSplus40
Kinetic study on leaching process of beryl with basic solution under microwave heating39
Front face shaping of the inner wall tiles in the COMPASS Upgrade tokamak39
Proposal of new electrode supports in NBI for breakdown incidence reduction39
Nuclear analysis of the DEMO divertor survey visible high-resolution spectrometer39
Microstructure and properties of La2O3-doped tungsten-based bulk material and its densification mechanism during spark plasma sintering process37
Supporting analysis for WCLL test blanket system safety37
Interactive simulations as a tool for logistics and maintenance of IFMIF-DONES37
Investigation of cracking behaviors in divertor armor-blocks under cyclic loading35
Methodology for radiofrequency electromagnetic analysis in the engineering of ITER Electron Cyclotron Heating Upper Launcher34
Shutdown dose rate assessment of the interspace components of wide angle viewing system diagnostic for ITER33
First steps of the overall integration design of CFETR32
Performance of fine-grained W/Cu plate prepared by explosive welding with high wave impedance confinement at room temperature31
Study of non-convergence problem of the integral method for polarizer design on the ECRH system29
Design of the removable shrouds for inertial-confinement-fusion cryotargets29
Design of ITER neutron flux monitor system back-end electronics29
Effect of He seeding on hydrogen isotope permeation in tungsten by H-D mixed plasma exposure29
Dispersion interferometry diagnostic at Globus-M228
DEMO – The main achievements of the Pre – Concept phase of the safety and environmental work package and the development of the GSSR27
Radiation control in deuterium, tritium and deuterium-tritium JET baseline plasmas – part I27
Exploring the potential of machine learning for real-time neutron emissivity tomography using the Vertical Neutron Camera of ITER27
Numerical investigation of Ne pellet formation for EAST shattered pellet injection system27
ITER DMS fast shutter prototype testing26
The engineering design of quarter size negative beam source for the comprehensive research facility for fusion technology26
Electromagnetic preliminary design of the real-time millimetre-wave radar system for the diagnostic of the IFMIF-DONES lithium target23
The Tritium Extraction eXperiment (TEX): A forced convection fusion blanket PbLi loop23
Improved strength and heat transfer of W/Cu joints via surface nano-activation of W23
Parameter study of L–H transition for plasma operation scenario development in JA DEMO22
Petri net modelling – A remote maintenance simulation approach for fusion remote maintenance equipment concepts assessment22
Scenario trajectory optimization and control on STEP22
Investigation of radiation power and carbon evaporation in infrared sensor bolometer21
Radio frequency designed a quadrature hybrid divider for the load-tolerant ICRF system on EAST21
Test blanket modules piping systems calculation method according to RCC-MRx code21
Development status of the HVPS and control system for KSTAR ECH system upgrade21
Influence of temperature gradients on helium diffusion and clustering in tungsten: A molecular dynamics study20
Experimental validation of the SPIDER accelerator design and grid developments19
Validation of NSFsim as a Grad-Shafranov equilibrium solver at DIII-D19
Contributions of MYRRHA to the European Fusion Energy Roadmap19
Data fusion of magnetic coils and Hall sensors using Kalman filtering19
Detection of MARFEs using visible cameras for disruption prevention19
Safety and interlock system for poloidal field power supply based on EPICS18
Numerical and experimental analysis of magneto-convective flows around pipes18
Proposal of a criterion to select the layout of bolometric diagnostics for robust plasma radiation reconstruction in fusion devices18
Creep behavior of EUROFER97–3 steel during neutron irradiation at 325 °C and 550 °C to 7–24 dpa18
Tungsten coated tiles for KSTAR PFC upgrade18
Installation, commissioning and testing of a low energy accelerator based 14-MeV neutron generator for lab scale fusion neutronics experiment18
Thermal analysis and optimization of the calorimeter verification prototype of a negative ion-based neutral beam injection system18
Electric potential on a WCLL TBM mock-up in MHD experiments as indication for flow distribution in breeder units17
An ultrafast digitizer for continuous measurements from microwave fusion diagnostics17
Development of the plasma scenario for EU-DEMO: Status and plans17
Development of real-time density feedback control on MAST-U in L-mode17
DEMO Divertor preliminary safety assessment16
Editorial Board16
Electrical diagnostics for high voltage tests in MITICA16
Modeling and quantitative prediction of dynamic atmosphere-soil behaviors linked to tritium discharge16
Investigation of glow discharge plasma energy distribution using a gridded energy analyzer considering plasma-facing materials related processes16
Development and modeling of a remote handling maintenance procedure for the IFMIF-DONES high flux test module electrical connectors bridge16
Overview of IFMIF-DONES diagnostics: Requirements and techniques16
Editorial Board16
A modular multilevel DC active power filter scheme based on optimal parameter design for the CFETR N-NBI accelerator grid power supply15
Improvement and test of high-voltage pulsed power supply for HFRC15
Preparation for Korean procurement scope of ITER sealing flanges15
Parametric FE model for the thermal and hydraulic optimization of a Plasma Facing Component equipped with sacrificial lattice armours for First Wall limiter application in EU-DEMO fusion reactor15
Solid state catalytic tritiation of deuterated polybutadiene through isotopic exchange and tritium addition15
Performances of three atmospheric dispersion models in predicting near-surface tritium concentration distribution15
An automatic online optics classification method used in the final optics recycling loop strategy15
The bonded area growth at diffusion bonding determined by the numerical modelling of Gleeble 3800 experiments and in comparison with the model by Hill and Wallach15
Development of double-walled bellows for ITER VUV spectrometer systems15
Impact analysis of power supply fault-state on magnets in fusion devices15
Development of a scintillator based fast-ion loss detector for the Wendelstein 7-X stellarator15
Effect of thermomechanical treatment on MX phase precipitation behavior in CLAM steel14
The structure design and kinematics analysis of the manipulator for the upper port remote maintenance in DEMO14
X-ray imaging crystal spectrometer (XICS) diagnostic on the HL-3 tokamak14
High frequency ultrasonic inspection of the bonded interface between a divertor monoblock and a cooling pipe14
An optical-input Maximum Likelihood Estimation feedback system demonstrated on tokamak horizontal equilibrium control14
Overview and first operation of the high temperature superconductor current leads during integrated commissioning of JT-60SA14
Investigation on flow instability in the first wall of CFETR WCCB blanket and preliminary design of the test section14
Status of JADE, an open-source software for nuclear data libraries V&V14
Realization of beam line components for ITER DNB system- lessons learnt14
Transient analysis of a locked rotor/shaft seizure accident involving the EU-DEMO WCLL Breeding Blanket primary cooling circuits14
Studies on the silver-coated patch with spot welding for the ITER Thermal Shield14
Engineering design and analysis of first wall on the high-magnetic-field-side for HL-2M tokamak14
Temperature dependence of surface microstructure of 316 L stainless steel exposed to low-energy hydrogen ion irradiation14
Thermal-hydraulic scaling of the prototypical mock-up for European DEMO HCPB breeding blanket14
Investigation into optimal feedforward control for remote handling of tokamak breeding blankets13
Influence of titanium on the clustering of vacancy, rhenium and osmium in tungsten-titanium alloys: First-principles study13
Modeling snowflake plasmas in RFX-mod2: A test bed for SOL and edge physics characterization13
The effect of pre-damage distribution on deuterium-induced blistering and retention in Tungsten13
Integrated design of breeding blanket and ancillary systems related to the use of helium or water as a coolant and impact on the overall plant design13
1D/2D benchmark experiments of aluminum alloy irradiated by 14 MeV neutrons for ICF facilities13
Retention of noble and rare isotope gases in plasma-facing components – Experience from the JET tokamak with the ITER-like wall13
Evaluation of a newly developed low reflection dummy load for high power millimeter waves13
Comparison of three key remote sensing technologies for mobile robot localization in nuclear facilities13
Determination of the activation energy of tritium diffusion in ceramic breeders by reactor power variation13
Design of a 170GHz quasi-optical notch filter for microwave-based diagnostics protection on the burning plasma device13
16Cr3Al-Hf ODS steel: Surface effects of high laser intensity of 1015 W/cm2 in ambiences of air, helium and vacuum13
Progress towards the validation of SIMMER-III code model for lead-lithium water chemical interaction13
Status and challenges for the concept design development of the EU DEMO Plant Electrical System12
Measurement of tritium release from Li2TiO3 breeder under fusion neutron irradiation by bubbling system12
Perspectives of a DCLL blanket for a future strong magnetic field fusion device12
Influence of thermomechanical treatment on mechanical properties of CLAM steel12
Design and manufacturing of tritium-carrier process pipes and associated guard-pipe for ITER Test Blanket Systems12
Real-time MHD feedback control system in Keda Torus eXperiment12
Research status of tungsten-based plasma-facing materials: A review12
Influence of plasma grid-masking on the results of early SPIDER operation12
Special tests on the first unit of the solid-state RF amplifiers for the ITER HNB and the NBTF experiments12
Neutron yield using a semi-Monte Carlo simulating method for D-T fusion neutron sources12
Three-dimensional modeling and simulation of RF cavity for a transmitter with bandwidth of 40–100 MHz at 100-kilowatt level12
A new 3MW ECRH system at 105 GHz for WEST12
2D simulations of inductive RF heating in the drivers of the SPIDER device12
Preliminary design and analysis of the back supporting structure for CFETR WCCB blanket12
Manufacturing of W-steel joint using plasma sprayed graded W/steel-interlayer with current assisted diffusion bonding12
Helium recovery and blanketing effect with the hydriding reaction of ZrCo12
Acceleration of cryogenic pellets for Shattered Pellet Injection11
Special behavior of alkali beam emission spectroscopy in low-ion-temperature plasma11
Neural network based visual servo for quick-change device alignment in context of fusion reactor remote maintenance11
Design and FEM modeling of a fire resistant cabinet for fusion environment11
Thermo-structural analysis of ITER divertor for normal operating conditions11
Radwaste analysis and package optimization with the F4E-radwaste tool and application to the ITER IVVS11
Contribution of electron density to plasma decomposition rate of methane11
Li6La3Ta1.5Y0.5O12 solid-state lithium sensor for molten alloys11
An allocation method of reliability goal for a compact fusion device11
Analytical solution of tokamak vibrations during axisymmetric plasma disruptions11
Development and status of high-voltage power supply and integrated control system for KSTAR ECH system11
3D high-fidelity automated neutronics guided optimization of fusion blanket designs11
Analysing the distribution of runaway electrons in the EAST tokamak based on SOFT11
Application of VERDI detectors for ITER materials activation product inventory characterization11
Draining analyses of the primary cooling circuits of the SPIDER Beam Source10
Conceptual design of the COMPASS-U control systems10
Molecular dynamics simulations of the effect of porosity on heat transfer in Li2TiO310
A more flexible design for MDSplus Device drivers10
Robustness of the E×B MDC prototype design for gyrotrons10
Commissioning and first operational experience with the new thyristor converter Group 7 of ASDEX Upgrade10
Multi-dimensional condensation behavior during ingress of coolant event experiments for fusion reactors with TRACE code10
Activated corrosion product contamination assessments of DEMO WCLL breeding blanket primary heat transport system10
Lessons learnt from manufacturing—Forging of tokamak components10
Design status of the neutron and gamma-ray diagnostics for the Divertor Tokamak Test facility10
LITEC: An experimental facility for the validation of the IFMIF-DONES Impurity Control System10
Investigation on the pressure drop characteristics of ITER thermal shield cooling pipes10
Fluid-structural analysis of the IFMIF-DONES outlet channel during nominal operation10
Thermal studies of liquid tin capillary porous system at the OLMAT high heat flux facility10
Signal-distribution-based crack detection for divertor monoblock inspection using eddy current testing10
Joining of self-passivating W-Cr-Y alloy to ferritic-martensitic steel by hot isostatic pressing10
Fabrication and test of a conceptual first wall containing titanium nitride as a tritium permeation barrier10
Stellaris: A high-field quasi-isodynamic stellarator for a prototypical fusion power plant10
Analysis of implementing a rail-based maintenance system into a HELIAS 5-B device10
Thermal-mechanical analysis and optimization on the critical components of the high temperature PbLi loop for CFETR10
New high-field side magnetic probe array system for three-dimensional magnetic fluctuation measurements on EAST10
Thermal effect on the modal characteristics of the rotor of a typical cryogenic turbine for helium refrigerator10
Feasibility of the EDICAM camera for runaway electron detection in JT-60SA disruptions10
Long pulse operation of neutral beam injector on EAST tokamak10
Elucidating the thermal response of W-Ta alloys with Transient Grating Spectroscopy, TEM and atomistic simulation10
Control upgrade for the TCV coils power supplies10
Design and research of bilateral teleoperation for CFETR tile assembly using haptic feedback10
Magnetic field and power consumption constraints for compact spherical tokamak power plants10
Pellet fragmentation studies for the ITER disruption mitigation system10
Development of experimental control system for regenerative heating process of high-speed cryo-adsorption pump10
Application of the different deconvolution methods to the neutron spectrum reconstruction from activation measurement10
RF conditioning to suppress multipactor discharge for helicon wave current drive in KSTAR9
High power experiment and heat load evaluation of transmission line for the ECH/CD system in JT-60SA9
Machine learning-based predictions of yield strength for neutron-irradiated ferritic/martensitic steels9
The effect of O impurity particle adsorption on the Cs/Mo (110) surface9
Kilogram scale throughput performance of the KATRIN tritium handling system9
RF design of helical long-wire traveling wave antenna for helicon current drive in KSTAR9
Deuterium retention properties of vanadium beryllide (Be12V) for advanced neutron multiplier applications9
EU-DEMO vacuum vessel port closure plate fastening developments9
Installation, thermal curing, qualification testing of divertor and position control coils in ADITYA-U tokamak9
Editorial Board9
Development of a Cherenkov probe with high time resolution for runaway electron measurements in the HL-2M tokamak9
Investigation of gas and plasma driven deuterium permeation through a vanadium membrane for particle exhaust application in a fusion reactor9
Lessons learned after three years of SPIDER operation and the first MITICA integrated tests9
Activation analysis and radwaste assessment of CFETR9
Progress of engineering design of CFETR cryogenic system9
Progress in the electromagnetic optimization of the CFETR CS coil9
The evolution of the interlocks for KSTAR9
Introduction on tritium transport analysis model for HCCP breeding blanket system9
Matching parameter estimation for high power Inductively coupled plasma sources using Machine learning techniques9
Effect of heat treatment on microstructure and mechanical property of ODS-CLAM-Zr steel9
Neutron irradiation response of explosion-welded CuCrZr/316LN joints for ITER application9
Effects of neutron irradiation on hydrogen isotope permeation on W-Re9
Shutdown dose rates in-cryostat outside the EU-DEMO vacuum vessel9
Suppression of runaway current by magnetic energy transfer in J-TEXT9
Influence of the orientation of the magnetic field on the MHD unaligned isothermal flows9
Editorial Board9
Achievement of precise assembly of the JT-60SA superconducting tokamak9
Development of manufacturing technology for the full-size WCCB module9
Final development and preliminary experiment progress of in-vessel resonant magnetic perturbation coils system on HL-3 tokamak9
Abstract9
Effect of diffusion interlayer and graded multi-interlayers on the reduction of thermal stress in tritium penetration barrier coating system9
Manufacturing, installation, commissioning and operation of endoscopes for monitoring water-cooled divertor in Wendelstein 7-X9
Editorial Board9
Study on electron beam welding process of the first wall of water-cooled ceramic breeder (WCCB) blanket9
Experimental investigation of the corrosion behavior of Eurofer97 steel in contact with Lithium ceramic breeder pebbles under specific Helium Cooled Pebble Bed breeding zone atmosphere9
Hydraulic analysis of the start-up monitoring module (STUMM) for IFMIF-DONES9
Supply and demand of tungsten in a fleet of fusion power plants9
Evaluation of AC losses in toroidal field magnets in the China Fusion Engineering Test Reactor9
Achieving effective bonding between W-75Cu composite and CuCrZr alloy via spark plasma sintering9
Editorial Board9
A review of pipe cutting, welding, and NDE technologies for use in fusion devices9
Data-driven disruption prediction using random forest in KSTAR9
Isotopic effect of proton conductivity in gadolinium sesquioxide8
Development of excitation controller for 300 MVA energy storage generator8
Flow-solid-heat coupled analyses of scandium target for deuterium- deuterium neutron generator8
Benefits of high-energy varistors in breakdown and fast discharge units8
Variable-curvature elephant trunk robot in nuclear industry8
ITER progresses into new baseline8
Analysis of the integral zeolite molecular sieve process for helium CPS application8
Editorial Board8
Development and optimization of a new control interface for the ASDEX upgrade high current converters8
The CHIMERA facility development programme8
Corrigendum to ‘Fracture-mechanical behaviour of ITER grade tungsten subjected to three different rolling processes’. Fusion Engineering and Design 184 (2022) 1133008
Concept for a multi-purpose EU-DEMO pellet launching system8
Development of TWA mock-up for TITAN8
On-line micro GC testing of protium analysis in DT fuels from TCAP products8
Design and analysis of actively-cooled, edge-transport diagnostic for long-pulsed operation in WEST8
Molecular dynamics simulations of deuterium bubble evolution in tungsten under neutron irradiation and non-irradiation conditions8
A Modelica dynamic model of a supercritical CO2 energy conversion system for EU-DEMO8
First characterization of the SPIDER beam AC component with the Beamlet Current Monitor8
Cascaded multilevel inverter for vertical stabilization and radial control power supplies8
Resonant power absorption in nonuniform toroidal helicon plasma sources8
Upgrade design and analysis of the quench tank of the IFMIF-DONES lithium target system8
Fault prediction of gyrotron system on test bench using a deep learning algorithm8
Status of HCCR TBM program for DEMO blanket8
Corrigendum to “The dynamic factor particle swarm optimization (DFPSO) to inverse kinematics of CMOR based on pose decomposition strategy” [Fusion Engineering and Design 197 (2023) 114047]8
Optimization effect of ribs distribution on electromagnetic structural response of CFETR vacuum vessel under MD8
Synthesis method of hydrophobic catalysts for the hydrogen activation with a controlled platinum distribution8
Development of bismuth metallic hall sensors for the HL-2A tokamak magnetic measurements8
Design and analysis of the CFETR cryostat8
Non-destructive radiological characterization applied to fusion waste management8
Control of electrochemical parameters for hydrogen permeation of CLF-1 steel8
Recent advances of the IFMIF-DONES central instrumentation and control systems engineering design8
Overview on electrical issues faced during the SPIDER experimental campaigns8
SMART materials for DEMO: Towards industrial production8
Research on signal measurement algorithm of circular dot matrix high current sensor8
Pre-conceptual design study of remote handling compatible attachment mechanisms for in-vessel components in DEMO tokamak8
Maintenance plan of the ITER Radial Neutron Camera: Verification and validation by virtual reality simulation8
An in-pile demonstrated platform for the evaluation of tritium extraction technologies in China Mianyang Research Reactor8
Normal spectral emissivity measurement of graphite in the temperature range between 200°C and 500°C8
0.066317081451416