Fusion Engineering and Design

Papers
(The TQCC of Fusion Engineering and Design is 4. 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 2022-01-01 to 2026-01-01.)
ArticleCitations
Steady-state Superconducting Advanced Spherical Tokamak Reactor (SASTR)112
Editorial Board100
Updating the build, test, and deploy systems for MDSplus82
Study of non-convergence problem of the integral method for polarizer design on the ECRH system73
Design of ITER neutron flux monitor system back-end electronics67
Radio frequency designed a quadrature hybrid divider for the load-tolerant ICRF system on EAST62
Mode purity evaluation of high-power millimeter wave transmission line by 3-port directional coupler59
The wide-angle infrared diagnostic for the first wall monitoring of the WEST tokamak57
Editorial Board54
Design of the removable shrouds for inertial-confinement-fusion cryotargets53
Development status of the HVPS and control system for KSTAR ECH system upgrade45
Microstructure and properties of La2O3-doped tungsten-based bulk material and its densification mechanism during spark plasma sintering process43
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 CICC41
Front face shaping of the inner wall tiles in the COMPASS Upgrade tokamak38
Editorial Board37
Effect of He seeding on hydrogen isotope permeation in tungsten by H-D mixed plasma exposure36
Soft X-ray tomography using the optimized regularization method in Alvand Tokamak33
Electromagnetic preliminary design of the real-time millimetre-wave radar system for the diagnostic of the IFMIF-DONES lithium target31
ITER DMS fast shutter prototype testing31
Exploring the potential of machine learning for real-time neutron emissivity tomography using the Vertical Neutron Camera of ITER30
Improved strength and heat transfer of W/Cu joints via surface nano-activation of W27
Methodology for radiofrequency electromagnetic analysis in the engineering of ITER Electron Cyclotron Heating Upper Launcher27
Proposal of a criterion to select the layout of bolometric diagnostics for robust plasma radiation reconstruction in fusion devices26
An ultrafast digitizer for continuous measurements from microwave fusion diagnostics25
Installation, commissioning and testing of a low energy accelerator based 14-MeV neutron generator for lab scale fusion neutronics experiment23
Safety and interlock system for poloidal field power supply based on EPICS23
Experimental validation of the SPIDER accelerator design and grid developments23
Tungsten coated tiles for KSTAR PFC upgrade22
Hydraulic characterization of the central cooling channel for the DEMO PF coil conductor22
Contributions of MYRRHA to the European Fusion Energy Roadmap21
Proposal of new electrode supports in NBI for breakdown incidence reduction21
Development of real-time density feedback control on MAST-U in L-mode21
Electrical diagnostics for high voltage tests in MITICA21
On the minimum size of tokamaks aimed at fusion energy gain with optimum plasma temperature20
Dispersion interferometry diagnostic at Globus-M220
Parameter study of L–H transition for plasma operation scenario development in JA DEMO19
Investigation of radiation power and carbon evaporation in infrared sensor bolometer19
Numerical investigation of Ne pellet formation for EAST shattered pellet injection system19
Test blanket modules piping systems calculation method according to RCC-MRx code19
Validation of NSFsim as a Grad-Shafranov equilibrium solver at DIII-D18
DEMO – The main achievements of the Pre – Concept phase of the safety and environmental work package and the development of the GSSR18
Data fusion of magnetic coils and Hall sensors using Kalman filtering18
Petri net modelling – A remote maintenance simulation approach for fusion remote maintenance equipment concepts assessment17
Exploring the stability of blanket pebble bed with plasma events17
Thermal analysis and optimization of the calorimeter verification prototype of a negative ion-based neutral beam injection system17
Interactive simulations as a tool for logistics and maintenance of IFMIF-DONES17
Electric potential on a WCLL TBM mock-up in MHD experiments as indication for flow distribution in breeder units17
Radiation control in deuterium, tritium and deuterium-tritium JET baseline plasmas – part I17
Detection of MARFEs using visible cameras for disruption prevention17
Mechanical and electrical performance of glass fiber reinforced plastic insulation for cryogenic application in fusion magnet irradiated in fast breeder reactor17
Overview of IFMIF-DONES diagnostics: Requirements and techniques17
Numerical and experimental analysis of magneto-convective flows around pipes17
Development and modeling of a remote handling maintenance procedure for the IFMIF-DONES high flux test module electrical connectors bridge17
Scenario trajectory optimization and control on STEP16
Fusion neutronics simulations with RMC: Key capabilities and techniques16
Development of the plasma scenario for EU-DEMO: Status and plans16
Structural behavior of electrical post-insulators for the MITICA Beam Source Mock-Up SOFT 202416
Exploratory thermal and fluid-dynamic assessment of a pin of the Helium cooled pebble bed breeding blanket concept with a modular pin monoblock design for the EU DEMO nuclear fusion reactor16
Nuclear analyses in support of the water-cooled lithium lead breeding blanket design development: a prospective strategy to achieve the tritium self-sufficiency16
Influence of temperature gradients on helium diffusion and clustering in tungsten: A molecular dynamics study16
Influence of thermal aging on the deuterium permeation and retention behavior in the CLAM Steel15
Modeling and quantitative prediction of dynamic atmosphere-soil behaviors linked to tritium discharge15
High frequency ultrasonic inspection of the bonded interface between a divertor monoblock and a cooling pipe15
Kinetic study on leaching process of beryl with basic solution under microwave heating15
The Tritium Extraction eXperiment (TEX): A forced convection fusion blanket PbLi loop15
Editorial Board15
Creep behavior of EUROFER97–3 steel during neutron irradiation at 325 °C and 550 °C to 7–24 dpa15
Investigation into optimal feedforward control for remote handling of tokamak breeding blankets15
Development of double-walled bellows for ITER VUV spectrometer systems15
Thermal-hydraulic scaling of the prototypical mock-up for European DEMO HCPB breeding blanket14
Measurement of tritium release from Li2TiO3 breeder under fusion neutron irradiation by bubbling system14
Engineering considerations for optical diagnostics of European DEMO14
Realization of beam line components for ITER DNB system- lessons learnt14
Impact analysis of power supply fault-state on magnets in fusion devices14
Development of a scintillator based fast-ion loss detector for the Wendelstein 7-X stellarator14
A modular multilevel DC active power filter scheme based on optimal parameter design for the CFETR N-NBI accelerator grid power supply13
An optical-input Maximum Likelihood Estimation feedback system demonstrated on tokamak horizontal equilibrium control13
The effect of pre-damage distribution on deuterium-induced blistering and retention in Tungsten13
Improvement and test of high-voltage pulsed power supply for HFRC13
A new 3MW ECRH system at 105 GHz for WEST13
Temperature dependence of surface microstructure of 316 L stainless steel exposed to low-energy hydrogen ion irradiation13
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 Wallach13
16Cr3Al-Hf ODS steel: Surface effects of high laser intensity of 1015 W/cm2 in ambiences of air, helium and vacuum13
Editorial Board12
Evaluation of a newly developed low reflection dummy load for high power millimeter waves12
Investigation of glow discharge plasma energy distribution using a gridded energy analyzer considering plasma-facing materials related processes12
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 reactor12
An automatic online optics classification method used in the final optics recycling loop strategy12
X-ray imaging crystal spectrometer (XICS) diagnostic on the HL-3 tokamak12
The structure design and kinematics analysis of the manipulator for the upper port remote maintenance in DEMO12
Modeling snowflake plasmas in RFX-mod2: A test bed for SOL and edge physics characterization12
Influence of plasma grid-masking on the results of early SPIDER operation12
Status of JADE, an open-source software for nuclear data libraries V&V12
Special tests on the first unit of the solid-state RF amplifiers for the ITER HNB and the NBTF experiments12
1D/2D benchmark experiments of aluminum alloy irradiated by 14 MeV neutrons for ICF facilities11
Neutron spectrometer based on a gas electron multiplier (GEM) detector for fusion reactors11
Development of a translation stage for beam studies in the negative ion source SPIDER11
A dynamic model of a power conversion system with indirect thermal energy storage for a pulsed fusion tokamak for use in design optimisation11
Perspectives of a DCLL blanket for a future strong magnetic field fusion device11
Retention of noble and rare isotope gases in plasma-facing components – Experience from the JET tokamak with the ITER-like wall11
Design of a 170GHz quasi-optical notch filter for microwave-based diagnostics protection on the burning plasma device11
Design and analysis of a SF6 gas insulating HV-bushing for CRAFT NNBI11
Progress towards the validation of SIMMER-III code model for lead-lithium water chemical interaction11
Engineering design and analysis of first wall on the high-magnetic-field-side for HL-2M tokamak11
Influence of thermomechanical treatment on mechanical properties of CLAM steel11
Performances of three atmospheric dispersion models in predicting near-surface tritium concentration distribution11
Defect structure evolution in early-stage neutron irradiated F82H and its model alloys at 363 K and 563K11
Influence of titanium on the clustering of vacancy, rhenium and osmium in tungsten-titanium alloys: First-principles study11
Status and challenges for the concept design development of the EU DEMO Plant Electrical System11
Real-time MHD feedback control system in Keda Torus eXperiment11
Water hammer analysis of valve closure scenarios in the ITER CCWS-1 cooling loop11
Investigation on flow instability in the first wall of CFETR WCCB blanket and preliminary design of the test section11
Transient analysis of a locked rotor/shaft seizure accident involving the EU-DEMO WCLL Breeding Blanket primary cooling circuits11
Assessment of the Runaway Electrons induced damage to the Tokamak First Wall11
Preparation for Korean procurement scope of ITER sealing flanges11
2D simulations of inductive RF heating in the drivers of the SPIDER device11
Evaluation of microstructural and mechanical properties of ARAA plates with various thicknesses10
Li6La3Ta1.5Y0.5O12 solid-state lithium sensor for molten alloys10
Development and status of high-voltage power supply and integrated control system for KSTAR ECH system10
Molecular dynamics simulations of the effect of porosity on heat transfer in Li2TiO310
Investigation on the pressure drop characteristics of ITER thermal shield cooling pipes10
Preliminary design and analysis of the back supporting structure for CFETR WCCB blanket10
A review of pipe cutting, welding, and NDE technologies for use in fusion devices10
LITEC: An experimental facility for the validation of the IFMIF-DONES Impurity Control System10
Acceleration of cryogenic pellets for Shattered Pellet Injection10
The manufacturing and assembly of the MITICA beam source and beam line components10
Design and manufacturing of tritium-carrier process pipes and associated guard-pipe for ITER Test Blanket Systems10
Thermal effect on the modal characteristics of the rotor of a typical cryogenic turbine for helium refrigerator10
Thermo-structural analysis of ITER divertor for normal operating conditions10
Contribution of electron density to plasma decomposition rate of methane10
One-dimensional simulations of nonlinear burn control in ITER10
Research status of tungsten-based plasma-facing materials: A review10
Blanket remote maintenance robot motion control based on nonlinear model predictive control and neural network10
Pellet fragmentation studies for the ITER disruption mitigation system10
Lessons learnt from manufacturing—Forging of tokamak components10
Special behavior of alkali beam emission spectroscopy in low-ion-temperature plasma10
Three-dimensional modeling and simulation of RF cavity for a transmitter with bandwidth of 40–100 MHz at 100-kilowatt level10
Achievement of precise assembly of the JT-60SA superconducting tokamak9
Neutron yield using a semi-Monte Carlo simulating method for D-T fusion neutron sources9
Robustness of the E×B MDC prototype design for gyrotrons9
Thermal studies of liquid tin capillary porous system at the OLMAT high heat flux facility9
Application of VERDI detectors for ITER materials activation product inventory characterization9
Analysis of implementing a rail-based maintenance system into a HELIAS 5-B device9
RF conditioning to suppress multipactor discharge for helicon wave current drive in KSTAR9
Fluid-structural analysis of the IFMIF-DONES outlet channel during nominal operation9
Final development and preliminary experiment progress of in-vessel resonant magnetic perturbation coils system on HL-3 tokamak9
Machine learning-based predictions of yield strength for neutron-irradiated ferritic/martensitic steels9
Fabrication and test of a conceptual first wall containing titanium nitride as a tritium permeation barrier9
Activation analysis and radwaste assessment of CFETR9
Activated corrosion product contamination assessments of DEMO WCLL breeding blanket primary heat transport system9
Control upgrade for the TCV coils power supplies9
Development of manufacturing technology for the full-size WCCB module9
Multi-dimensional condensation behavior during ingress of coolant event experiments for fusion reactors with TRACE code9
Neural network based visual servo for quick-change device alignment in context of fusion reactor remote maintenance9
Commissioning and first operational experience with the new thyristor converter Group 7 of ASDEX Upgrade9
Progress of engineering design of CFETR cryogenic system9
Analytical solution of tokamak vibrations during axisymmetric plasma disruptions9
Surrogate modeling for MHD flows in liquid metal fusion blankets: Initial assessment with analytical solutions9
Feasibility of the EDICAM camera for runaway electron detection in JT-60SA disruptions9
Computing material volume fractions on a superimposed mesh as applied to Monte Carlo particle transport simulations9
Design and research of bilateral teleoperation for CFETR tile assembly using haptic feedback9
Design status of the neutron and gamma-ray diagnostics for the Divertor Tokamak Test facility9
A more flexible design for MDSplus Device drivers9
Progress in the electromagnetic optimization of the CFETR CS coil9
Design and FEM modeling of a fire resistant cabinet for fusion environment9
Development of experimental control system for regenerative heating process of high-speed cryo-adsorption pump9
An allocation method of reliability goal for a compact fusion device9
Radwaste analysis and package optimization with the F4E-radwaste tool and application to the ITER IVVS9
Elucidating the thermal response of W-Ta alloys with Transient Grating Spectroscopy, TEM and atomistic simulation9
Data-driven disruption prediction using random forest in KSTAR9
Signal-distribution-based crack detection for divertor monoblock inspection using eddy current testing9
Magnetic field and power consumption constraints for compact spherical tokamak power plants9
Thermal-mechanical analysis and optimization on the critical components of the high temperature PbLi loop for CFETR9
Predictive modelling of tritium breeding ratio (TBR) in EU DEMO WCLL blankets: OpenMC simulations and analytical insights8
Analysis of the integral zeolite molecular sieve process for helium CPS application8
Construction and preliminary discharge investigation of a proton-boron linear plasma device8
Research on signal measurement algorithm of circular dot matrix high current sensor8
DEMO in-vessel equatorial coils for power-exhaust and fast plasma control8
Development of a Cherenkov probe with high time resolution for runaway electron measurements in the HL-2M tokamak8
Conceptual design proposal for the EU-DEMO electron cyclotron ex-vessel waveguide system with enhanced remote maintainability8
Editorial Board8
Maintenance plan of the ITER Radial Neutron Camera: Verification and validation by virtual reality simulation8
An OpenMC model of the SPARC tokamak for the diagnostic scoping studies8
Effects of cell parameters on accurate calculation of activation dose after DT explosion for local hot spots in laser-driven ICF facilities8
Real-time monitoring system for detection and characterization of thermal events on WEST Tokamak: Implementation and first results8
Supply and demand of tungsten in a fleet of fusion power plants8
Effect of heat treatment on microstructure and mechanical property of ODS-CLAM-Zr steel8
Long pulse operation of neutral beam injector on EAST tokamak8
New high-field side magnetic probe array system for three-dimensional magnetic fluctuation measurements on EAST8
3D high-fidelity automated neutronics guided optimization of fusion blanket designs8
Dynamic analysis of the COMPASS-U tokamak for the design of foundation8
Conceptual design of poloidal horseshoe limiter layout for JA DEMO8
Overview on electrical issues faced during the SPIDER experimental campaigns8
Editorial Board8
Upgrade design and analysis of the quench tank of the IFMIF-DONES lithium target system8
Mechanical design of ITER radial neutron camera Ex-Port system8
Pre-conceptual design study of remote handling compatible attachment mechanisms for in-vessel components in DEMO tokamak8
Matching parameter estimation for high power Inductively coupled plasma sources using Machine learning techniques8
Fault prediction of gyrotron system on test bench using a deep learning algorithm8
Deuterium retention properties of vanadium beryllide (Be12V) for advanced neutron multiplier applications8
Experimental investigation of the corrosion behavior of Eurofer97 steel in contact with Lithium ceramic breeder pebbles under specific Helium Cooled Pebble Bed breeding zone atmosphere8
Influence of viscosity adjuster and its concentration on dip coating solution for Er2O38
Stellaris: A high-field quasi-isodynamic stellarator for a prototypical fusion power plant8
Effects of neutron irradiation on hydrogen isotope permeation on W-Re8
Application of the Gaede effect to the neutralizer of DTT neutral beam injector8
Improved algorithm of finding the next volume in direct CAD method for fusion neutronics analysis8
First characterization of the SPIDER beam AC component with the Beamlet Current Monitor8
Abstract8
Development and optimization of a new control interface for the ASDEX upgrade high current converters8
Achieving effective bonding between W-75Cu composite and CuCrZr alloy via spark plasma sintering8
Editorial Board8
Effect of diffusion interlayer and graded multi-interlayers on the reduction of thermal stress in tritium penetration barrier coating system8
Manufacturing, installation, commissioning and operation of endoscopes for monitoring water-cooled divertor in Wendelstein 7-X8
The evolution of the interlocks for KSTAR8
Lessons learned after three years of SPIDER operation and the first MITICA integrated tests8
Development of advanced ternary beryllium intermetallic compounds7
Study on T production using high-temperature gas-cooled reactor for DEMO fusion reactor − H absorption properties of Zr sphere with Ni coating7
Fusion waste requirements for tritium control: Perspectives and current research7
Design and heat transfer analysis of new single-screw pellet injector for EAST tokamak7
Control of electrochemical parameters for hydrogen permeation of CLF-1 steel7
Upgrade of the neutral beam heating system on the TCV tokamak – second high energy neutral beam7
Editorial Board7
RF design of helical long-wire traveling wave antenna for helicon current drive in KSTAR7
Environment-aware motion planning for EAST Optical Diagnostic Beam Orientation Robot7
Simulation and experimental study on dynamic characteristics of isolated contact for 100 kA pyrobreaker7
Analyses of vacuum vessel pressure suppression system during divertor LOCA for Helium cooled pebble bed DEMO7
Design study of superconducting coil system for JA DEMO7
A high-performance electromagnetic code to simulate high-temperature superconductors7
Preliminary fault analysis of EFCC system in the Divertor Tokamak Test (DTT) facility7
Numerically investigation of the neutron irradiation swelling on the mechanical and structural evolution of beryllium pebble bed7
ITER progresses into new baseline7
Design and analysis of actively-cooled, edge-transport diagnostic for long-pulsed operation in WEST7
Solid-state radiofrequency amplifier technology for fusion applications7
EU-DEMO vacuum vessel port closure plate fastening developments7
Shutdown dose rates in-cryostat outside the EU-DEMO vacuum vessel7
Comparison of a fast low spatial resolution inversion method and peaking factors for the detection of anomalous radiation patterns and disruption prediction7
The CHIMERA facility development programme7
Integrated design of tokamak building concepts including ex-vessel maintenance7
Plasma focus device as a tool for comparing radiation resistance in tungsten and molybdenum using high-energy hydrogen ions7
Blanket test facility for mockup testing on water cooled ceramic breeder blanket system7
Influence of Li on the behavior of H and point defects in vanadium alloys7
Preliminary calibration procedure for the Phase1 neutron and gamma-ray diagnostics of the Divertor Tokamak Test (DTT) facility7
Corrigendum to “Total Ionizing Dose Estimation of ITER Upper Port Remote Handling Equipment” [Fusion Engineering and Design volume 202 (2024) 114359]7
Research and economic evaluation on novel pulse superconducting magnet power supply topology with energy storage for fusion devices7
Development of excitation controller for 300 MVA energy storage generator7
High power experiment and heat load evaluation of transmission line for the ECH/CD system in JT-60SA7
Investigation of gas and plasma driven deuterium permeation through a vanadium membrane for particle exhaust application in a fusion reactor7
Recent advances of the IFMIF-DONES central instrumentation and control systems engineering design7
Evaluation of AC losses in toroidal field magnets in the China Fusion Engineering Test Reactor7
TRL analysis of IFMIF-DONES7
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