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 2022-08-01 to 2026-08-01.)
ArticleCitations
Editorial Board129
Proposal of a criterion to select the layout of bolometric diagnostics for robust plasma radiation reconstruction in fusion devices83
Experimental validation of the SPIDER accelerator design and grid developments75
Hydraulic characterization of the central cooling channel for the DEMO PF coil conductor65
Proposal of new electrode supports in NBI for breakdown incidence reduction61
Kinetic study on leaching process of beryl with basic solution under microwave heating36
Study of non-convergence problem of the integral method for polarizer design on the ECRH system35
Radio frequency designed a quadrature hybrid divider for the load-tolerant ICRF system on EAST32
Editorial Board30
Front face shaping of the inner wall tiles in the COMPASS Upgrade tokamak29
Development status of the HVPS and control system for KSTAR ECH system upgrade29
Methodology for radiofrequency electromagnetic analysis in the engineering of ITER Electron Cyclotron Heating Upper Launcher27
Editorial Board27
Exploring the stability of blanket pebble bed with plasma events26
Numerical and experimental analysis of magneto-convective flows around pipes25
Parameter study of L–H transition for plasma operation scenario development in JA DEMO24
Test blanket modules piping systems calculation method according to RCC-MRx code23
Data fusion of magnetic coils and Hall sensors using Kalman filtering23
Influence of thermal aging on the deuterium permeation and retention behavior in the CLAM Steel22
Influence of temperature gradients on helium diffusion and clustering in tungsten: A molecular dynamics study22
Electromagnetic preliminary design of the real-time millimetre-wave radar system for the diagnostic of the IFMIF-DONES lithium target21
Detection of MARFEs using visible cameras for disruption prevention21
Numerical investigation of Ne pellet formation for EAST shattered pellet injection system21
ITER DMS fast shutter prototype testing21
Scenario trajectory optimization and control on STEP21
Exploring the potential of machine learning for real-time neutron emissivity tomography using the Vertical Neutron Camera of ITER20
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 CICC20
An ultrafast digitizer for continuous measurements from microwave fusion diagnostics20
Microstructure and properties of La2O3-doped tungsten-based bulk material and its densification mechanism during spark plasma sintering process20
The wide-angle infrared diagnostic for the first wall monitoring of the WEST tokamak20
On the minimum size of tokamaks aimed at fusion energy gain with optimum plasma temperature19
Dispersion interferometry diagnostic at Globus-M219
Installation, commissioning and testing of a low energy accelerator based 14-MeV neutron generator for lab scale fusion neutronics experiment18
Mode purity evaluation of high-power millimeter wave transmission line by 3-port directional coupler18
Structural behavior of electrical post-insulators for the MITICA Beam Source Mock-Up SOFT 202418
Mechanical and electrical performance of glass fiber reinforced plastic insulation for cryogenic application in fusion magnet irradiated in fast breeder reactor18
Contributions of MYRRHA to the European Fusion Energy Roadmap18
Nuclear analyses in support of the water-cooled lithium lead breeding blanket design development: a prospective strategy to achieve the tritium self-sufficiency17
Steady-state Superconducting Advanced Spherical Tokamak Reactor (SASTR)17
Design of the removable shrouds for inertial-confinement-fusion cryotargets17
Overview of IFMIF-DONES diagnostics: Requirements and techniques17
Electrical diagnostics for high voltage tests in MITICA17
The Tritium Extraction eXperiment (TEX): A forced convection fusion blanket PbLi loop17
Safety and interlock system for poloidal field power supply based on EPICS16
Effect of He seeding on hydrogen isotope permeation in tungsten by H-D mixed plasma exposure16
Interactive simulations as a tool for logistics and maintenance of IFMIF-DONES16
Tungsten coated tiles for KSTAR PFC upgrade16
PAV-2: a new mock-up to investigate niobium membrane-PAV performances optimization in PbLi systems16
Development and modeling of a remote handling maintenance procedure for the IFMIF-DONES high flux test module electrical connectors bridge16
Creep behavior of EUROFER97–3 steel during neutron irradiation at 325 °C and 550 °C to 7–24 dpa16
Petri net modelling – A remote maintenance simulation approach for fusion remote maintenance equipment concepts assessment16
Development of real-time density feedback control on MAST-U in L-mode16
Evaluating solid-state neutron detectors for measuring 14 MeV neutrons at high temperatures15
Validation of NSFsim as a Grad-Shafranov equilibrium solver at DIII-D15
Electric potential on a WCLL TBM mock-up in MHD experiments as indication for flow distribution in breeder units15
The manufacturing and assembly of the MITICA beam source and beam line components15
Fusion neutronics simulations with RMC: Key capabilities and techniques15
Radiation control in deuterium, tritium and deuterium-tritium JET baseline plasmas – part I15
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 reactor15
1D/2D benchmark experiments of aluminum alloy irradiated by 14 MeV neutrons for ICF facilities15
Development of a translation stage for beam studies in the negative ion source SPIDER15
Improved strength and heat transfer of W/Cu joints via surface nano-activation of W15
Updating the build, test, and deploy systems for MDSplus15
Soft X-ray tomography using the optimized regularization method in Alvand Tokamak15
Efficient calculation of magnetic fields from ferromagnetic materials near strong electromagnets, and application to stellarator coil optimization15
Investigation of radiation power and carbon evaporation in infrared sensor bolometer15
Numerical investigation of 3D MHD pressure drop in a prototypical fusion blanket manifold using OpenFOAM14
Blanket remote maintenance robot motion control based on nonlinear model predictive control and neural network14
A dynamic model of a power conversion system with indirect thermal energy storage for a pulsed fusion tokamak for use in design optimisation14
Editorial Board14
Real-time MHD feedback control system in Keda Torus eXperiment14
Investigation on flow instability in the first wall of CFETR WCCB blanket and preliminary design of the test section14
X-ray imaging crystal spectrometer (XICS) diagnostic on the HL-3 tokamak14
Advancement in the development of remote handling tools for the volumetric neutron source blanket14
Realization of beam line components for ITER DNB system- lessons learnt14
High frequency ultrasonic inspection of the bonded interface between a divertor monoblock and a cooling pipe14
Engineering design and analysis of first wall on the high-magnetic-field-side for HL-2M tokamak14
Development of a scintillator based fast-ion loss detector for the Wendelstein 7-X stellarator14
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 Wallach14
Impact analysis of power supply fault-state on magnets in fusion devices14
Thermal-hydraulic scaling of the prototypical mock-up for European DEMO HCPB breeding blanket14
An optical-input Maximum Likelihood Estimation feedback system demonstrated on tokamak horizontal equilibrium control13
16Cr3Al-Hf ODS steel: Surface effects of high laser intensity of 1015 W/cm2 in ambiences of air, helium and vacuum13
Assessment of the Runaway Electrons induced damage to the Tokamak First Wall13
Modeling snowflake plasmas in RFX-mod2: A test bed for SOL and edge physics characterization13
Temperature dependence of surface microstructure of 316 L stainless steel exposed to low-energy hydrogen ion irradiation13
Investigation into optimal feedforward control for remote handling of tokamak breeding blankets13
Editorial Board13
Neutron spectrometer based on a gas electron multiplier (GEM) detector for fusion reactors13
Evaluation of a newly developed low reflection dummy load for high power millimeter waves13
Performances of three atmospheric dispersion models in predicting near-surface tritium concentration distribution13
The effect of pre-damage distribution on deuterium-induced blistering and retention in Tungsten13
The structure design and kinematics analysis of the manipulator for the upper port remote maintenance in DEMO13
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 reactor13
An automatic online optics classification method used in the final optics recycling loop strategy13
Measurement of tritium release from Li2TiO3 breeder under fusion neutron irradiation by bubbling system13
Modeling and quantitative prediction of dynamic atmosphere-soil behaviors linked to tritium discharge12
Pre-conceptual design of ECE Imaging for real time NTM control12
Water hammer analysis of valve closure scenarios in the ITER CCWS-1 cooling loop12
Progress towards the validation of SIMMER-III code model for lead-lithium water chemical interaction12
Perspectives of a DCLL blanket for a future strong magnetic field fusion device12
Mechanical analysis of tail structures in the next-generation fully superconducting tokamak CS HTS12
Defect structure evolution in early-stage neutron irradiated F82H and its model alloys at 363 K and 563K12
Retention of noble and rare isotope gases in plasma-facing components – Experience from the JET tokamak with the ITER-like wall12
A modular multilevel DC active power filter scheme based on optimal parameter design for the CFETR N-NBI accelerator grid power supply12
Special tests on the first unit of the solid-state RF amplifiers for the ITER HNB and the NBTF experiments12
Investigation of glow discharge plasma energy distribution using a gridded energy analyzer considering plasma-facing materials related processes12
Status of JADE, an open-source software for nuclear data libraries V&V12
Design of a 170GHz quasi-optical notch filter for microwave-based diagnostics protection on the burning plasma device12
Development of double-walled bellows for ITER VUV spectrometer systems12
Design and analysis of a SF6 gas insulating HV-bushing for CRAFT NNBI12
Influence of plasma grid-masking on the results of early SPIDER operation12
Improvement and test of high-voltage pulsed power supply for HFRC12
Engineering considerations for optical diagnostics of European DEMO12
Special behavior of alkali beam emission spectroscopy in low-ion-temperature plasma11
3D high-fidelity automated neutronics guided optimization of fusion blanket designs11
Research status of tungsten-based plasma-facing materials: A review11
Transient analysis of a locked rotor/shaft seizure accident involving the EU-DEMO WCLL Breeding Blanket primary cooling circuits11
Contamination tolerance of two NEG pumps: A comparative experimental study of air and water-vapor exposure11
Power supply design aspects for the divertor plasma operations in ADITYA-U tokamak11
Analysis of implementing a rail-based maintenance system into a HELIAS 5-B device11
Construction and preliminary discharge investigation of a proton-boron linear plasma device11
Control upgrade for the TCV coils power supplies11
Li6La3Ta1.5Y0.5O12 solid-state lithium sensor for molten alloys11
Acceleration of cryogenic pellets for Shattered Pellet Injection11
Influence of thermomechanical treatment on mechanical properties of CLAM steel11
2D simulations of inductive RF heating in the drivers of the SPIDER device11
Data-driven disruption prediction using random forest in KSTAR11
Experimental study and analysis of turn insulation conductivity during arc propagation in superconducting fusion magnets11
Radwaste analysis and package optimization with the F4E-radwaste tool and application to the ITER IVVS11
Design and FEM modeling of a fire resistant cabinet for fusion environment11
An allocation method of reliability goal for a compact fusion device11
Contribution of electron density to plasma decomposition rate of methane11
Design and manufacturing of tritium-carrier process pipes and associated guard-pipe for ITER Test Blanket Systems11
Preparation for Korean procurement scope of ITER sealing flanges11
A new 3MW ECRH system at 105 GHz for WEST11
Control, diagnostic, and instrumentation systems of the Helios fusion power plant11
Feasibility of the EDICAM camera for runaway electron detection in JT-60SA disruptions11
Three-dimensional modeling and simulation of RF cavity for a transmitter with bandwidth of 40–100 MHz at 100-kilowatt level11
Application of VERDI detectors for ITER materials activation product inventory characterization11
Commissioning and first operational experience with the new thyristor converter Group 7 of ASDEX Upgrade10
Development of experimental control system for regenerative heating process of high-speed cryo-adsorption pump10
Investigation of the ultra-wideband polarizer for high power millimeter wave system10
Fluid-structural analysis of the IFMIF-DONES outlet channel during nominal operation10
Design and research of bilateral teleoperation for CFETR tile assembly using haptic feedback10
Design and implementation of a safety and security enhanced IEEE 1588 clock synchronization system for Tokamak10
Investigation on the pressure drop characteristics of ITER thermal shield cooling pipes10
Signal-distribution-based crack detection for divertor monoblock inspection using eddy current testing10
Machine learning-based predictions of yield strength for neutron-irradiated ferritic/martensitic steels10
Lessons learnt from manufacturing—Forging of tokamak components10
RF conditioning to suppress multipactor discharge for helicon wave current drive in KSTAR10
Elucidating the thermal response of W-Ta alloys with Transient Grating Spectroscopy, TEM and atomistic simulation10
Multi-dimensional condensation behavior during ingress of coolant event experiments for fusion reactors with TRACE code10
Thermal effect on the modal characteristics of the rotor of a typical cryogenic turbine for helium refrigerator10
Influence of viscosity adjuster and its concentration on dip coating solution for Er2O310
Corrigendum to “Temperature-dependent ATR-FTIR calibration using a two-state spectral model for deuterium detection in water” [Fusion Engineering and Design 225 (2026)115656]10
New high-field side magnetic probe array system for three-dimensional magnetic fluctuation measurements on EAST10
One-dimensional simulations of nonlinear burn control in ITER10
Predictive modelling of tritium breeding ratio (TBR) in EU DEMO WCLL blankets: OpenMC simulations and analytical insights10
Thermal-mechanical analysis and optimization on the critical components of the high temperature PbLi loop for CFETR10
Progress in the electromagnetic optimization of the CFETR CS coil10
Commissioning and first results obtained by the C/O monitor system at the Wendelstein7‑X stellarator10
Design status of the neutron and gamma-ray diagnostics for the Divertor Tokamak Test facility10
Robustness of the E×B MDC prototype design for gyrotrons10
Cascaded filtering with dynamic parameter optimization for composite-noise suppression in gyrotron power supplies10
Neural network based visual servo for quick-change device alignment in context of fusion reactor remote maintenance10
Investigation of gas and plasma driven deuterium permeation through a vanadium membrane for particle exhaust application in a fusion reactor9
Achieving effective bonding between W-75Cu composite and CuCrZr alloy via spark plasma sintering9
A review of pipe cutting, welding, and NDE technologies for use in fusion devices9
Development and optimization of a new control interface for the ASDEX upgrade high current converters9
A more flexible design for MDSplus Device drivers9
Development of a Cherenkov probe with high time resolution for runaway electron measurements in the HL-2M tokamak9
Development of manufacturing technology for the full-size WCCB module9
LITEC: An experimental facility for the validation of the IFMIF-DONES Impurity Control System9
Neutron yield using a semi-Monte Carlo simulating method for D-T fusion neutron sources9
Fault prediction of gyrotron system on test bench using a deep learning algorithm9
Dynamic analysis of the COMPASS-U tokamak for the design of foundation9
Environment-aware motion planning for EAST Optical Diagnostic Beam Orientation Robot9
Editorial Board9
Long pulse operation of neutral beam injector on EAST tokamak9
EU-DEMO vacuum vessel port closure plate fastening developments9
Stellaris: A high-field quasi-isodynamic stellarator for a prototypical fusion power plant9
Maintenance plan of the ITER Radial Neutron Camera: Verification and validation by virtual reality simulation9
Activated corrosion product contamination assessments of DEMO WCLL breeding blanket primary heat transport system9
Computing material volume fractions on a superimposed mesh as applied to Monte Carlo particle transport simulations9
Pellet fragmentation studies for the ITER disruption mitigation system9
Final development and preliminary experiment progress of in-vessel resonant magnetic perturbation coils system on HL-3 tokamak9
Upgrade design and analysis of the quench tank of the IFMIF-DONES lithium target system9
Effects of cell parameters on accurate calculation of activation dose after DT explosion for local hot spots in laser-driven ICF facilities9
Improved algorithm of finding the next volume in direct CAD method for fusion neutronics analysis9
First characterization of the SPIDER beam AC component with the Beamlet Current Monitor9
Fabrication and test of a conceptual first wall containing titanium nitride as a tritium permeation barrier9
Editorial Board9
Lessons learned after three years of SPIDER operation and the first MITICA integrated tests9
Pre-conceptual design study of remote handling compatible attachment mechanisms for in-vessel components in DEMO tokamak9
Thermal studies of liquid tin capillary porous system at the OLMAT high heat flux facility9
Molecular dynamics simulations of the effect of porosity on heat transfer in Li2TiO39
Surrogate modeling for MHD flows in liquid metal fusion blankets: Initial assessment with analytical solutions9
Evaluation of microstructural and mechanical properties of ARAA plates with various thicknesses9
Editorial Board9
Control of electrochemical parameters for hydrogen permeation of CLF-1 steel9
Reducing laser plasma instability in inertial confinement fusion by polarization smoothing based on stress birefringence8
Isotope effect in the interaction of gallium-lithium alloy with hydrogen and deuterium at high temperatures8
Study of the influence of vertical magnetic field on the propagation and coupling of ICRF waves under CN-H1 non-axisymmetric magnetic field configuration8
Conceptual design of poloidal horseshoe limiter layout for JA DEMO8
The evolution of the interlocks for KSTAR8
Evaluation of AC losses in toroidal field magnets in the China Fusion Engineering Test Reactor8
Design and prototype validation of a cage-type coaxial octocopter system for fusion reactor vacuum vessel inspection8
Corrigendum to ‘Fracture-mechanical behaviour of ITER grade tungsten subjected to three different rolling processes’. Fusion Engineering and Design 184 (2022) 1133008
Effect of 2/1 tearing mode on radiation asymmetry during disruptions on J-TEXT8
Mechanical design of ITER radial neutron camera Ex-Port system8
DEMO in-vessel equatorial coils for power-exhaust and fast plasma control8
Cascaded multilevel inverter for vertical stabilization and radial control power supplies8
Operational planning of magnetic confinement fusion power plants using a MIP unit-commitment model8
Mathematical modelling and application of the topology optimization for CFETR WCCB blanket8
Overview on electrical issues faced during the SPIDER experimental campaigns8
Molecular dynamics simulations of deuterium bubble evolution in tungsten under neutron irradiation and non-irradiation conditions8
Comparison of a fast low spatial resolution inversion method and peaking factors for the detection of anomalous radiation patterns and disruption prediction8
Strategies and solutions for engineering challenges during the assembly of divertor and position control coils in ADITYA-U tokamak8
Matching parameter estimation for high power Inductively coupled plasma sources using Machine learning techniques8
Computational fluid dynamics Study with heat transfer inside the embedded cooling channels for prototype ion extractor grid-1 and comparison with experimental results8
Directives, codes, standards and other requirements applicable to the design and manufacture of components in the ITER project8
Recent advances of the IFMIF-DONES central instrumentation and control systems engineering design8
The CHIMERA facility development programme8
ITER progresses into new baseline8
Overview of university-class Tokamak TRUST: Preliminary characterization of plasma scenario and disruption studies8
Simulation and experimental study on dynamic characteristics of isolated contact for 100 kA pyrobreaker8
Introduction on tritium transport analysis model for HCCP breeding blanket system8
SMART materials for DEMO: Towards industrial production8
Effect of heat treatment on microstructure and mechanical property of ODS-CLAM-Zr steel8
Manufacturing, installation, commissioning and operation of endoscopes for monitoring water-cooled divertor in Wendelstein 7-X8
Research on signal measurement algorithm of circular dot matrix high current sensor8
Real-time monitoring system for detection and characterization of thermal events on WEST Tokamak: Implementation and first results8
Variable-curvature elephant trunk robot in nuclear industry8
Effects of neutron irradiation on hydrogen isotope permeation on W-Re8
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
Supply and demand of tungsten in a fleet of fusion power plants8
Shutdown dose rates in-cryostat outside the EU-DEMO vacuum vessel8
Analysis of the integral zeolite molecular sieve process for helium CPS application8
High temperature vacuum brazing of tungsten to tungsten alloy with structural material8
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
An OpenMC model of the SPARC tokamak for the diagnostic scoping studies8
Benefits of high-energy varistors in breakdown and fast discharge units8
Application of the Gaede effect to the neutralizer of DTT neutral beam injector8
Conceptual design proposal for the EU-DEMO electron cyclotron ex-vessel waveguide system with enhanced remote maintainability8
Design and heat transfer analysis of new single-screw pellet injector for EAST tokamak8
Preliminary calibration procedure for the Phase1 neutron and gamma-ray diagnostics of the Divertor Tokamak Test (DTT) facility8
EU-DEMO Concept design of chemical and volume control system: Design main drivers and challenges8
Installation, thermal curing, qualification testing of divertor and position control coils in ADITYA-U tokamak8
Deuterium retention properties of vanadium beryllide (Be12V) for advanced neutron multiplier applications8
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