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 2021-04-01 to 2025-04-01.)
ArticleCitations
Assessment of measurement performance for a low field side IDTT plasma position reflectometry system86
Microstructure and properties of La2O3-doped tungsten-based bulk material and its densification mechanism during spark plasma sintering process76
Characterization of aged Li4SiO4 pebbles performance66
Helium impurity measurement in hydrogen isotope mixtures by gas chromatography64
Comparison of deuterium retention in rolled and recrystallized tungsten with and without pre-damage55
COMPASS-U plasma-facing components: Towards a full W first wall coverage52
Updating the build, test, and deploy systems for MDSplus48
Configuration design and prototype development of a remote-centered parallel welding robot43
Introduction41
Preliminary architecture design for human-in-the-loop control of robotic equipment in remote handling tasks: Case study on the NEFERTARI project38
Wall cratering upon high velocity normal dust impact38
Online monitoring of tritium in water using uncladed plastic scintillating fibers37
Studies on high voltage dc cable connection to supply the acceleration grids of the Neutral Beam Injector for DTT36
Thermal-hydraulic analysis of alternative cable-in-conduit conductors for the European DEMO hybrid central solenoid35
Parameter study of L–H transition for plasma operation scenario development in JA DEMO35
Progress in the optimization of wall conditioning techniques for the reliable operation of KSTAR plasmas34
Comprehensive assessment of nuclear heating in ITER superconducting magnets using a full-tokamak 360° model34
Investigation of pipelines defect localization for fusion reactor by using T(0,1) mode ultrasonic guided waves33
Kinetic study on leaching process of beryl with basic solution under microwave heating33
Development of a PbLi heat exchanger for EU DEMO fusion reactor: Experimental test and system code assessment32
Engineering design and testing of rotary joints’ driving systems for the CFETR multi-purpose overload robot31
Improved strength and heat transfer of W/Cu joints via surface nano-activation of W30
Limiters for DEMO wall protection: Initial design concepts & technology options29
Benchmarking of emergent radiation transport codes for fusion neutronics applications28
Fast visible camera diagnostic for dual shattered pellet injections at KSTAR27
Microwave ion source with dual helical antenna for diagnostics neutral beam of ALBORZ tokamak27
Simulation of the surface cracking behavior in Al2O3 coating as tritium penetration barrier by extended finite element analysis26
Design study of a cryogenic distillation column for hydrogen isotope separation system26
The DTT device: Preliminary remote maintenance strategy26
REMOVED: Upgrade of the APEC code: Implementation of halo currents and induced currents in the coils26
The design and implementation of distributed architecture in the CMOR motion control system26
Scenario trajectory optimization and control on STEP26
Design and analysis of a pulsed coil power supply for the DIII-D tokamak25
Feasibility evaluation and pre-conceptual design of the Iter Tokamak systems monitor25
In-vessel components for initial operation of JT-60SA25
Thickness-variation measurement at downstream regions for Li target of fusion neutron sources24
Selective adsorption properties of layered titanate for tritiated water23
Nuclear analyses for the integration of ITER equatorial Port 223
Mechanical design of a Fast Shutter for the ITER disruption mitigation system23
Thermo-mechanical analysis of the components in the launcher transmission line of ITER ex-port plug collective Thomson scattering23
Simulation and control of welding distortion for the CFETR equatorial port extension mock-up22
Evaluation on Nonirradiated Thermo-mechanical Response of WCCB TBM Following RCC-MRx21
Performance evaluation of tungsten for ITER divertor toward mass production21
Full scale test facility for operability verification of tokamak pressure suppression system at sub-atmospheric conditions21
Electrical diagnostics for high voltage tests in MITICA21
Conceptual design of the Gas Injection and Vacuum System for DTT NBI20
Analysis of supercritical carbon dioxide Brayton cycles for a helium-cooled pebble bed blanket DEMO-like fusion power plant20
Object-oriented modeling, simulation and control of a 6-DoF parallel kinematic manipulator for remote handling in DONES facility20
Assessment of radiation dose rate in main building area of A-FNS facility20
Development of sub-miniaturised testing methodology for W/Cu joints extracted from the ITER-specification monoblock19
An obstacle avoidance path planning algorithm to simulate hyper redundant manipulators for tokamaks maintenance19
Exploring the potential of machine learning for real-time neutron emissivity tomography using the Vertical Neutron Camera of ITER19
Benchmark of beam acceleration codes on a high voltage negative ion accelerator for fusion with a new hypothesis on the beam meniscus19
"Plasma and Fusion Cloud" Data analysis environment18
Simulation analysis of the motion accuracy of the ECRH launcher steering mechanism based on ADAMS18
Study of microstructure & mechanical properties of TIG welded aluminized 9Cr-1Mo steel18
Gas pressure casting technique for manufacturing of W/OFHC-Cu monoblock17
Editorial Board17
Editorial Board17
Design and analysis of cooling water system for ECRH and ICRF testing bench17
Upgrade of the cathode HVPS system for 4.6 GHz LHCD on EAST using high speed PSM17
Concept selection for the preliminary DTT remote maintenance strategy17
Use of MAXFEA-ANSYS tool to study the Electro-Magnetic behaviour of the new ST40 inner vacuum chamber proposal during a plasma VDE16
Deuterium permeation through liquid tin supported by a nickel substrate16
A new subsequence similarity retrieval method based on inverted index in EAST16
Design and thermal-hydraulic analysis for CFETR divertor OVT in consideration of RH compatibility16
Improvement of SPIDER diagnostic systems16
Assessment of a bolted-flange connection for ITER Test Blanket Module16
Magnetic control of DTT alternative plasma configurations16
The modeling and analysis for the natural frequency adjustments of Vehicle Manipulator for the ITER Blanket Remote Handling System16
SPIDER on-line data visualization tool16
New method for reshaping of the WEST Lower Hybrid launcher to reach long pulse operation16
Lifetime assessment of the modified grounded grid in the negative ion source SPIDER15
Remote maintenance scenario of the caesium ovens and beam source of the ITER heating neutral beam15
Contributions of MYRRHA to the European Fusion Energy Roadmap15
Estimation of the power dissipation on the casing of DTT toroidal field coil during a fast plasma disruption15
Mechanical and electrical performance of glass fiber reinforced plastic insulation for cryogenic application in fusion magnet irradiated in fast breeder reactor15
The final design of the ITER Interlock Discharge Loop Interface Boxes (DLIB) and its compliance with the IEC 61508 standard15
Experimental study and discrete element method analysis of impact of vibration on pebble packing15
Mode purity evaluation of high-power millimeter wave transmission line by 3-port directional coupler15
Radio frequency designed a quadrature hybrid divider for the load-tolerant ICRF system on EAST15
Evaluation of transmission efficiency of the ECH/CD transmission lines in integrated commissioning phase on JT-60SA15
Concept design of automatic connector for maintenance cask of EU-DEMO and CFETR15
Structural design and analysis of EAST TCWS pipeline14
Experimental research on blowout process development of the EAST divertor14
Simulation of plasma scenarios for CFETR phase II based on engineering design parameters14
Evolution of microstructure in neutron irradiated cold rolled tungsten and its correlation with hardness14
Feasibility study of neutral beam injection in Thailand Tokamak-114
Study of the linear mercury diffusion pump with the fixed mass-flow-rate model by direct simulation Monte Carlo method14
Editorial Board14
Development of a thermo-mechanical behaviour model adapted to the ITER vacuum vessel material14
Conceptual design of a heavy ion beam probe diagnostic for HL-2M tokamak14
Optical tomography of the plasma on the PROTO-SPHERA experiment13
Modelling activity in support of MITICA high voltage system protections13
Thermal analyses of the W7-X plasma vessel for operation phase 213
Concluding remarks13
Control system for Thomson scattering diagnostic on XuanLong-50 spherical tokamak13
Investigation of atmospheric tritiated water vapor level around the Fukushima Daiichi nuclear power plant13
Critical current degradation behaviour of various REBCO tapes under uniaxial strain13
A method for assessing 3D decay heat and temperature considering accurate distributions of the decay gamma fields13
Study on performance of horizontal displacement control system of J-TEXT Tokamak under limiter and divertor configuration13
A method for automated modeling of plasma shape control response in tokamaks13
Mechanical impact of electromagnetic transients on the European DEMO divertor. Part 1: Vertical displacement event13
Development of new analytical tools for tritium transport modelling13
Embedded conductors in solidified molten metal for winding packs for high-field stellarators13
Acknowledgments13
Editorial Board12
Design and implement of control system for HUST field-reversed configuration device12
The wide-angle infrared diagnostic for the first wall monitoring of the WEST tokamak12
Hydraulic assessment of cooling circuit for CFETR W/Cu divertor12
Optimization of the overall Toroidal Field Coil cryomagnetic system at the pre-conceptual design phase of the European DEMO fusion reactor12
Study of RHQT-processed Nb3Al multifilamentary rectangular tape strand to be applied to a fusion magnet12
Editorial Board12
Protective behavior of tea catechins against DNA double strand breaks produced by radiations with different linear energy transfer12
Editorial Board12
Optimization of target alignment in inertial confinement fusion facilities based on redundant measurements12
Maxwell force analysis of CN HCCB TBM based on preliminary design12
Numerical calculations on liquid-metal magnetohydrodynamic flow in rectangular channel with wavelike uneven walls12
The research activities on test platform of high payload transporter joint for a tokamak12
Conductor design and performance analysis for CFETR magnet12
Integrated structural FE analyses of MITICA plant12
Editorial Board12
Maturation of critical technologies and systems design12
Design and position analysis of 2PUU-2PSS parallel mechanism for auxiliary assembly in DEMO vacuum vessel11
Design and preliminary experimental results of 5 MW-NBI arc power supply for HL-2M tokamak11
Application of MCNP unstructured mesh in the design process of the ITER EC-UL M3 mirror11
Position estimation of current-carrying filament using different magnetic sensors in ADITYA-U tokamak11
Design and analysis of redundant electro-hydraulic-driven manipulator for tokamak vacuum vessel11
Characteristics of purge gas flow in regular and random closed packed pebble beds through CFD-DEM11
Investigation of radiation power and carbon evaporation in infrared sensor bolometer11
Effect of non-nominal port gaps on nuclear responses in ITER11
Li2TiO3 pebble fabrication by freeze granulation & freeze drying method11
Radiation level in the DEMO tokamak complex due to activated flowing water: Impact on the architecture of the building11
Design for the distributed data locator service for multi-site data repositories11
Advances in Additive Manufacturing of fusion materials11
Total ionizing dose estimation of ITER upper port remote handling equipment11
Editorial Board11
Optimization of the metallic vessel-wall effect on the magnetic diagnostics calibration in ADITYA-U tokamak11
Neutronics analysis and activation calculation for tungsten used in the DEMO divertor targets: A comparative study between the effects of WCLL and HCPB blanket, different W compositions and chromium11
Test blanket modules piping systems calculation method according to RCC-MRx code11
Design and engineering challenges of a multi-energy hard x-ray camera for long-pulse profile measurements at WEST tokamak11
An optimized and flexible configuration for the magnetic filter in the SPIDER experiment10
Numerical and experimental analysis of magneto-convective flows around pipes10
Interactive simulations as a tool for logistics and maintenance of IFMIF-DONES10
First-principles study of the energetics of Fe interstitial clusters in vanadium10
Structural and thermal fluid dynamics analyses of the ITER Pressure Suppression System considering no stable steam condensation regimes10
An integral methodological framework for the thermo-mechanical analysis and structural integrity assessment of the European TBM sets10
ITER Toroidal Interferometer and Polarimeter (TIP) beam refraction in 3D density profiles10
Development of a compact real-time process gas analysis system for tritium accountancy for a DEMO fusion reactor by an application of laser Raman spectroscopy10
Overview of IFMIF-DONES diagnostics: Requirements and techniques10
Plasma current profile reconstruction for EAST based on Bayesian inference10
Development of a novel power module based on pulse step modulation10
Performance assessment of plasma current measurement at JET using fibre optics current sensor10
Investigation on low cycle fatigue properties of CLAM steel electron beam welded joint at 550 °C10
Thermal and structural analysis of TCABR vacuum vessel during baking process10
Erosion resistance test of SiC mirror sample for ITER divertor VUV spectrometer10
Upgrade and application of the gas puff imaging system in EAST10
Research on the thermal hydraulic design of COOL blanket for CFETR10
Influence of various gases and water vapors on the processes of tritium release from two-phase lithium ceramics10
DEMO Divertor preliminary safety assessment10
Thermal hydraulic transient analysis of ITER safety-relevant secondary cooling water system10
Potassium and sodium vapor diffusion pump development for fusion system10
Application of a multiphysics simulation tool to an in-box LOCA in the WCLL TBM test section of the LIFUS5/Mod4 facility10
Development of the high temperature PbLi experimental facility for CFETR10
Comparative study of ITER conform tungsten grades exposed to high heat flux and neutron irradiation damage10
Fluid-dynamic and thermo-mechanical analyses of the Monoblock Mitre Bend for the ITER electron cyclotron Upper launcher10
Development of the multi-chord CO2 interferometer on HFRC10
Preliminary investigation of neutron shielding compounds for ARC-class tokamaks10
Editorial Board10
Corrigendum to “Development of double-walled bellows for ITER VUV spectrometer systems” [Fusion Engineering and Design 207 (2024) 114643]10
Investigation of cracking behaviors in divertor armor-blocks under cyclic loading9
Study of a stainless steel porous membrane for recovering tritium from Pb-Li alloys: Assessment of mass transfer coefficient9
Development of real-time density feedback control on MAST-U in L-mode9
Fabrication and characterization of ceramic-iron joint coating for electrical insulation9
Approach to startup inventory for viable commercial fusion power plant9
As built design, commissioning and integration of the SPIDER and NBTF central safety systems9
Integration of LiPb loops for WCLL BB of European DEMO9
Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System9
Thermal analysis of the EAST tokamak9
Multipurpose ion beam analysis chamber for fusion material science applications9
Symmetries of 13C tracer deposition in EAST D and He plasmas investigated on the sub-mm to 100 mm scale by deuteron nuclear reaction analysis9
Managing the complexity of plasma physics in control systems engineering9
Preliminary analysis of an in-box LOCA in the breeding unit of the WCLL TBM for the ITER reactor with SIMMER-IV code9
Composites and additive manufacturing for high-field coil supports for stellarators9
Prediction of unusual plasma discharge by using Support Vector Machine9
Free boundary equilibrium determination of HL-3 discharges9
A remote detection method for leak location of external ports in a tokamak: Theory and preliminary experimental validation9
Waste management strategy for EU DEMO: Status, challenges and perspectives9
RELAP5/Mod3.3 MHD module development and validation: WCLL-TBM mock-up model9
The development of a Sustained High Power Density (SHPD) facility9
LIPAc RF power system: design and main practical implementation issues9
Preliminary thermal-hydraulic influence of the poloidal nonuniform neutron wall loading on the CFETR HCCB blanket9
Analysis of transport-activation internal coupling method implemented in Monte Carlo code cosRMC9
Nuclear analysis of the DEMO divertor survey visible high-resolution spectrometer9
Multi-scale lumped modeling of micro-channels cooling structure for W7-X divertor unit target module9
Multidisciplinary optimization of the waveguide transmission line for ITER HFS reflectometry9
Microstructure and mechanical properties of laser beam welded joints of China low-activation ferritic/martensitic steel with cerium addition9
High heat flux components with beryllium armour: From the small-scale mock-ups to the full-scale prototype of the ITER first wall panel9
Re-evaluation of shielding ability and induced activity of KSTAR with increased neutron yields9
Methodology for radiofrequency electromagnetic analysis in the engineering of ITER Electron Cyclotron Heating Upper Launcher9
Design of a 15 T hybrid superconducting magnet9
PACTITER-OSCAR comparison in ACPs determination for the ITER WCLL-TBS Water Cooling System9
Material flow planning in fusion test facilities9
Preparation of coated Li2TiO3 and Li4SiO4 pebbles by fluidized bed chemical vapor deposition for advanced tritium breeders9
Assessment of the relevancy of ENEA Water Loop facility with respect to ITER WCLL TBS Water Cooling System by considering their thermal-hydraulic performances9
Improvement of core snubber model based on modified saturation-wave theory9
A shutdown dose rates analysis of the Korean fusion demonstration reactor using MCNP5 mesh-based R2S approach9
Numerical investigation of Ne pellet formation for EAST shattered pellet injection system9
3D neutronic analysis on compact fusion reactors: PHITS-OpenMC cross-comparison9
Design and test of a mitigation system against voltage ringing in MITICA Acceleration Grid Power Supply8
Measurement of leakage neutron spectra for aluminium with D-T fusion neutrons and validation of evaluated nuclear data8
Proposal of new electrode supports in NBI for breakdown incidence reduction8
RAMI analysis of the Collective Thomson Scattering system front-end – Part2 – reliability block diagram analysis8
The EU strategy for solving the DEMO exhaust problem8
Plasma position measurement with collimated neutron flux monitor diagnostics on JET8
First beam extraction experiment from a prototype filament-arc driven negative ion source8
Relaxation of compressive stress in gamma-irradiated Viton™ fluoroelastomer8
Design and procurement of the Drying System for SPIDER beam source8
Optimization of helicon wave off-axis current drive in CFETR tokamak8
Estimation of tritium inventory in exhaust detritiation system for fusion test device in the initial tritium recovery operation8
Shutdown dose rate assessment of the interspace components of wide angle viewing system diagnostic for ITER8
Microstructural and mechanical characterization of self-passivating W-Eurofer joints processed by brazing technique8
Analysis, design, and testing of mechanical switch for the backup protection of switching network unit in fusion device8
Developments on actuator management, plasma state reconstruction, and control on ASDEX Upgrade8
An ultrafast digitizer for continuous measurements from microwave fusion diagnostics8
Structural design and preliminary feasibility analysis of a new stabilizing plate for the advanced tokamak in MD event8
Observation of surface deformation of tungsten exposed to single pulsed high heat flux and magnetic field for divertor design8
Numerical study on water draining process pushed by nitrogen in EAST upper divertor8
Monte Carlo simulations of W-Ta alloys under helium ion bombardment8
Integration issues on tritium management of the European DEMO Breeding Blanket and ancillary systems8
Benchmark analysis of in-vacuum vessel LOCA scenarios for code-to-code comparison8
Fatigue life prediction of hypervapotron for CFETR divertor8
Development of shutdown dose rate calculation code based on cosRMC and application to benchmark analysis8
Evaluation of neutron dose rates at the TCV tokamak facility8
Performance of fine-grained W/Cu plate prepared by explosive welding with high wave impedance confinement at room temperature8
Calibration of the KIT test setup for the cooling tests of a gyrotron cavity full-size mock-up equipped with mini-channels8
First results from the NORTH tokamak8
Optimal control of the electron temperature profile in DIII-D using machine learning surrogate models8
GSE-YOLOv5s: A lightweight visual detection method for first wall tile and bolts (Holes) in CFETR8
The beamline for the ITER heating neutral beam injectors: A case study for development and procurement of high heat flux components8
Robustness of ZAO based NEG pump solutions for fusion applications8
Thermal-hydraulic study of the DEMO divertor cassette body cooling circuit equipped with a liner and two reflector plates8
Liquid metal MHD flow influence on heat transfer phenomena in fusion reactor blankets8
Conceptual design of primary heat transfer system for CFETR power extraction system8
Supporting analysis for WCLL test blanket system safety8
Optimization of the gravity support in CFETR vacuum vessel8
Stray radiation energy fluxes in ITER based on a multiresonator model8
On the fabrication of ultrafine-grained potassium-doped tungsten: Mechanical milling and spark plasma sintering of K-doped W powder prepared by evaporation-condensation method8
Lithium vapour-box divertor module design for investigating vapour shielding performance and lithium transport in linear plasma generator Magnum-PSI8
Impact of W monoblock damage on EAST operations in recent campaigns8
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