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 2020-05-01 to 2024-05-01.)
ArticleCitations
Overview of recent ITER TBM Program activities63
Consolidated design of the HCPB Breeding Blanket for the pre-Conceptual Design Phase of the EU DEMO and harmonization with the ITER HCPB TBM program58
Divertor of the European DEMO: Engineering and technologies for power exhaust53
DTT - Divertor Tokamak Test facility: A testbed for DEMO52
Progress of the conceptual design of the European DEMO breeding blanket, tritium extraction and coolant purification systems46
Status of maturation of critical technologies and systems design: Breeding blanket46
On the road to ITER NBIs: SPIDER improvement after first operation and MITICA construction progress44
The DEMO magnet system – Status and future challenges42
DEMO physics challenges beyond ITER42
Engineering design of the CFETR machine37
Design and preliminary analyses of the new Water Cooled Lithium Lead TBM for ITER36
Required, achievable and target TBR for the European DEMO34
On the standards and practices for miniaturized tensile test – A review33
Preliminary design of the COMPASS upgrade tokamak33
LIBS measurements inside the FTU vessel mock-up by using a robotic arm30
Eurofusion-DEMO Divertor - Cassette Design and Integration29
An overview of the numerical methods for tokamak plasma equilibrium computation implemented in the NICE code29
Development of load specifications for the design of the breeding blanket system28
Tokamak cooling systems and power conversion system options28
Pre-conceptual design of EU DEMO balance of plant systems: Objectives and challenges28
Key design integration issues addressed in the EU DEMO pre-concept design phase28
Manufacturing and high heat flux testing of flat-type W/Cu/CuCrZr mock-up by HIP assisted brazing process28
Conceptual design of HTS magnets for fusion nuclear science facility27
Role of heat-treatment and filler on structure-property relationship of dissimilar welded joint of P22 and F69 steel27
DEMO – The main achievements of the Pre – Concept phase of the safety and environmental work package and the development of the GSSR27
Deployment of multiple shattered pellet injection systems in KSTAR27
Development of anti-permeation and corrosion barrier coatings for the WCLL breeding blanket of the European DEMO26
Current status and future perspectives of EU ceramic breeder development26
Maturation of critical technologies for the DEMO balance of plant systems26
Plasma-facing components damage and its effects on plasma performance in EAST tokamak26
Surface roughness and finishing techniques in selective laser melted GRCop-84 copper for an additive manufactured lower hybrid current drive launcher25
CAKE: Consistent Automatic Kinetic Equilibrium reconstruction25
Status and future development of Heating and Current Drive for the EU DEMO25
Materials for in-vessel components25
Microstructure formation mechanism and corrosion behavior of FeCrCuTiV two-phase high entropy alloy prepared by different processes25
SPIDER plasma grid masking for reducing gas conductance and pressure in the vacuum vessel25
ITER assembly phase: Progress toward first plasma24
Performance assessment of thick W/Cu graded interlayer for DEMO divertor target24
The EU DEMO staged design approach in the Pre-Concept Design Phase24
Influence of PbLi hydraulic path and integration layout on MHD pressure losses24
Structural stability, electronic structures, mechanical properties and debye temperature of W-Re alloys: A first-principles study24
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 design24
Tritium release behavior of Li2TiO3 and 2Li2TiO3-Li4SiO4 biphasic ceramic pebbles fabricated by microwave sintering23
Flush-mounted Langmuir probes in the WEST tokamak divertor23
Conceptual design of a liquid-metal divertor for the European DEMO23
Development of a set of movable electrostatic probes to characterize the plasma in the ITER neutral beam negative-ion source prototype23
Development of the plasma scenario for EU-DEMO: Status and plans23
The pre-concept design of the DEMO tritium, matter injection and vacuum systems23
Experimental study of hypervapotron channel with square fin structure for divertor cooling by one-side, electric joule heating system22
Integrated design strategy for EU-DEMO first wall protection from plasma transients22
Nuclear design of Divertor Tokamak Test (DTT) facility21
Design and assessment of a new divertor plasma facing component containing the Hypervapotron cooling channel and monoblock-type armor21
Plasma-surface interaction experimental device: PSIEC and its first plasma exposure experiments on bulk tungsten and coatings21
The Material Plasma Exposure eXperiment: Mission and conceptual design21
Diffusion bonding W and RAFM-steel with an Fe interlayer by hot isostatic pressing20
Development of Y2O3 dispersion strengthened Cu alloy using Cu6Y and Cu2O addition through the MA-HIP process20
Containment structures and port configurations20
Nuclear performances of the water-cooled lithium lead DEMO reactor: Neutronic analysis on a fully heterogeneous model20
The first implementation of active detachment feedback control in EAST PCS19
Structural lifetime assessment for the DEMO divertor targets: Design-by-analysis approach and outstanding issues19
An optimized and flexible configuration for the magnetic filter in the SPIDER experiment19
Development of a concept and basis for the DEMO diagnostic and control system19
MHD flow in liquid metal blankets: Major design issues, MHD guidelines and numerical analysis19
The issue of Tritium in DEMO coolant and mitigation strategies19
Industrial-scale manufacturing experience of titanium beryllide block for DEMO blanket application19
Integration issues on tritium management of the European DEMO Breeding Blanket and ancillary systems19
Conceptual design of a beam source for negative neutral beam injector of CRAFT facility18
Test Series D experimental results for SIMMER code validation of WCLL BB in-box LOCA in LIFUS5/Mod3 facility18
Numerical study of magneto-convection flows in a complex prototypical liquid-metal fusion blanket geometry18
Tritium release and retention in beryllium and titanium beryllide after neutron irradiation up to damage doses of 23-38 dpa18
3D modelling of MHD mixed convection flow in a vertical duct with transverse magnetic field and volumetric or surface heating18
Integration concept of an Electron Cyclotron System in DEMO18
Achievement of the ITER NBI ion source parameters for hydrogen at the test facility ELISE and present Status for deuterium17
Simultaneous H/D/T and 3He/4He absolute concentration measurements with an optical Penning gauge on JET17
RF discharge mirror cleaning system development for ITER diagnostics17
Power supply system for large negative ion sources: Early operation experience on the SPIDER experiment17
LIBS measurements inside the FTU vacuum vessel by using a robotic arm17
Nuclear analysis of the Water cooled lithium lead DEMO reactor17
Role of the heterogeneity in microstructure on the mechanical performance of the Autogenous Gas Tungsten Arc (GTA) welded dissimilar joint of F/M P91 and SS304L steel17
Resolution and geometric limitations in laser powder bed fusion additively manufactured GRCop-84 structures for a lower hybrid current drive launcher17
Thermal-hydraulic characteristics of purge gas in a rectangular packed pebble bed of a fusion reactor using DEM-CFD and porous medium analyses17
Effect of porosity on thermal conductivity of Li2TiO3 ceramic compact17
Isotopic effect of proton conductivity in gadolinium sesquioxide16
Nuclear analyses for the design of the ITER-like plasma facing components vertical targets of the DEMO divertor16
European DEMO first wall shaping and limiters design and analysis status16
EU DEMO Remote Maintenance System development during the Pre-Concept Design Phase16
Microstructural and elemental evolution of polycrystalline α-SiC irradiated with ultra-high-fluence helium ions before and after annealing16
Conceptual study of the remote maintenance of the DEMO breeding blanket16
Impact of plasma thermal transients on the design of the EU DEMO first wall protection16
Engineering design of a Permeator Against Vacuum mock-up with niobium membrane16
Experimental investigation of liquid metal MHD flow entering a flow channel insert16
Progress of the R&D programme to develop a metal foil pump for DEMO15
Ingress of Coolant Event simulation with TRACE code with accuracy evaluation and coupled DAKOTA Uncertainty Analysis15
The plan forward for EU DEMO15
Recent progress in the design of the K-DEMO divertor15
Effects of bed dimension, friction coefficient and pebble size distribution on the packing structures of the pebble bed for solid tritium breeder blanket15
Correlation study on tensile properties of Cu, CuCrZr and W by small punch test and uniaxial tensile test15
Features of the in-situ experiments on studying of tritium release from lithium ceramic Li2TiO3 using vacuum extraction method15
Design and analysis of the equatorial inboard WCCB blanket module for CFETR15
A new array eddy current testing probe for inspection of small-diameter tubes in Tokamak fusion devices15
Interfacial microstructures, residual stress and mechanical analysis of hot isostatic pressing diffusion bonded joint of 93W–4.9Ni–2.1Fe alloy and 30CrMnSiNi2A steel15
Mechanical properties of three kinds of ITER-Grade pure tungsten with different manufacturing processes15
Co-extracted electrons and beam inhomogeneity in the large negative ion source SPIDER15
Effects of sintering conditions on the microstructure of Li2TiO3 tritium breeding materials15
Progress of DTT ECRH system design15
Limiters for DEMO wall protection: Initial design concepts & technology options15
Characterization of the soft zone in dissimilar welds joint of 2.25Cr-1Mo and lean duplex LDX2101 steel14
Preliminary sensitivity analysis for an ex-vessel LOCA without plasma shutdown for the EU DEMO WCLL blanket concept14
Nuclear response of additive manufactured GRCop-84 copper for use in Lower hybrid launchers in a fusion environment14
The CFETR tritium plant: Requirements and design progress14
A composite coating of GO-Al2O3 for tritium permeation barrier14
Status and challenges for the concept design development of the EU DEMO Plant Electrical System14
Numerical simulation of 3D magnetohydrodynamic liquid metal flow in a spatially varying solenoidal magnetic field14
Improvements in the SPIDER RF system14
Smart Tungsten-based Alloys for a First Wall of DEMO14
Monitoring the plasma radiation profile with real-time bolometer tomography at JET14
Design, fabrication and comprehensive properties of the novel thermal neutron shielding Gd/316L composites14
Grain refinement and mechanical properties improvements in a high strength Cu–Ni–Si alloy during multidirectional forging14
MHD pressure drop estimate for the WCLL in-magnet PbLi loop14
Alternatives for upgrading the EU DCLL breeding blanket from MMS to SMS14
Developments on the tritium extraction and recovery system for HCPB14
Dynamic modelling of the helium-cooled DEMO fusion power plant with an auxiliary boiler in Apros14
Optimizing the EU-DEMO pellet fuelling scheme14
Investigation of the DEMO WCLL Breeding Blanket Cooling Water Activation14
The design and optimisation of a monoblock divertor target for DEMO using thermal break interlayer13
Modeling of hydrogen isotopes release from lithium ceramics Li2TiO3 during in-situ experiments using vacuum extraction method13
PETRA: A generalised real-time event detection platform at JET for disruption prediction, avoidance and mitigation13
Characterization of an ultra-compact neutron source based on an IEC fusion device and its prospective applications in radiography13
Test blanket modules (ITER) and breeding blanket (DEMO): History of major fabrication technologies development of HCLL and HCPB and status13
RF losses in selective laser melted GRCop-84 copper waveguide for an additively manufactured lower hybrid current drive launcher13
EU-DEMO divertor: Cassette design and PFCs integration at pre-conceptual stage13
In-situ oxidation of aluminized stainless-steel to form alumina as tritium permeation barrier coating13
Microstructures and mechanical properties of reduced activation ferritic/martensitic steel fabricated by laser melting deposition13
Optimization of tritium breeding ratio in ARC reactor13
Development of high strength and high electrical conductivity Cu-Cr-Zr alloy through friction stir processing13
Effect of thermal aging on metallurgical, tensile and impact toughness performance of electron beam welded AISI 316 SS joints13
Assessment of SIMMER-III code in predicting Water Cooled Lithium Lead Breeding Blanket “in-box-Loss of Coolant Accident”13
Development of an assistant program for CAD-to-cosRMC modelling13
Optical design of ex-vessel components for the Wide Angle Viewing System diagnostic for ITER13
Non-contact strain evaluation for miniature tensile specimens of neutron-irradiated F82H by digital image correlation13
Thermal-hydraulic analysis of the DEMO WCLL elementary cell: BZ tubes layout optimization13
Design of the Water-Cooled Ceramic Breeder blanket for CFETR13
RAMI evaluation of the beam source for the DEMO neutral beam injectors13
MHD forced convection flow in dielectric and electro-conductive rectangular annuli13
High temperature superconductors for fusion applications and new developments for the HTS CroCo conductor design13
Experimental results of multiple shattered pellet injection systems in KSTAR13
On the role of integrated computer modelling in fusion technology12
Progress of water cooled ceramic breeder test blanket module system12
The competing effects of temperature and neutron irradiation on the microstructure and mechanical properties of ITER grade tungsten12
Parametric design study of a substrate material for a DEMO sacrificial limiter12
Joining tungsten with steel for DEMO: Simultaneous brazing by Cu-Ti amorphous foils and heat treatment12
Oxidation behavior analysis of a ferritic ODS steel in supercritical Water12
Towards a 1.5 MW, 140 GHz gyrotron for the upgraded ECRH system at W7-X12
Composition optimization of high strength and ductility ODS alloy based on machine learning12
Dynamic accuracy ant colony optimization of inverse kinematic (DAACOIK) analysis of multi-purpose deployer (MPD) for CFETR remote handling12
Virtual and Augmented Reality Use Cases for Fusion Design Engineering12
Experimental study on critical current of bent ReBCO tapes in CORC type cable12
Investigation of heat transfer in a steam generator bayonet tube for the development of PbLi technology for EU DEMO fusion reactor12
Numerical simulations of MHD flows in a conduit that contracts in the magnetic field direction12
Integral modelling of the ITER cooling water systems radiation source for applications outside of the Bio-shield12
Performance of the first neutral beam injector at the Wendelstein 7-X stellarator12
Update of electromagnetic loads on HCPB breeding blanked for DEMO 2017 configuration12
Wendelstein 7-X on the path to long-pulse high-performance operation12
On the numerical assessment of the thermal-hydraulic operating map of the DEMO Divertor Plasma Facing Components cooling circuit12
Remarks on the performance of the EU DCLL breeding blanket adapted to DEMO 201712
Status and future developments of the Linear IFMIF Prototype Accelerator (LIPAc)12
Conceptual design of the supercritical CO2 cooled lithium lead blanket for CFETR12
Tungsten–chromium–yttrium alloys as first wall armor material: Yttrium concentration, oxygen content and transmutation elements12
The EUROfusion materials property handbook for DEMO in-vessel components—Status and the challenge to improve confidence level for engineering data12
RF discharge mirror cleaning for ITER optical diagnostics using 60 MHz very high frequency12
Particle-resolved simulation of randomly packed pebble beds with a novel fluid-solid coupling method12
Overview of the CFETR remote handling system and the development progress12
Evolution of microstructure in neutron irradiated cold rolled tungsten and its correlation with hardness12
Design overview of ex-vessel components for the Wide Angle Viewing System diagnostic for ITER Equatorial Port 1211
Effect of thermomechanical treatment on MX phase precipitation behavior in CLAM steel11
Electrothermal design of DC busbars for fusion facilities11
Experimental Qualification of New Instrumentation for Lead-Lithium Eutectic in IELLLO Facility11
The EU strategy for solving the DEMO exhaust problem11
Influence of Thermal Aging on Metallurgical, Mechanical and Corrosion Performance of Electron Beam Welded 18mm Thick AISI 31611
Electromagnetic coupling phenomena in co-axial rectangular channels11
Effect of thermal cycles on structure and deuterium permeation of Al2O3 coating prepared by MOD method11
European TBM programme: First elements of RoX and technical performance assessment for DEMO breeding blankets11
Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System11
A digital twin concept for the development of a DEMO maintenance logistics modelling tool11
Progress in engineering design of CFETR toroidal field superconducting magnet11
Determination of the activation energy of tritium diffusion in ceramic breeders by reactor power variation11
Neutronics and shielding design of CFETR HCCB blanket11
Technological aspects in blanket design: Effects of micro-alloying and thermo-mechanical treatments of EUROFER97 type steels after neutron irradiation11
EU-DEMO design space exploration and design drivers11
Analysis of promising technologies of DEMO-FNS fuel cycle11
DEMO structural materials qualification and development11
Parametric study of the TF coil design for the European DEMO11
Development of the automatic void generation module in GEOUNED conversion tool11
First ITER CS module test results11
Preliminary safety analysis of an in-vessel LOCA for the EU-DEMO WCLL blanket concept11
Integration of LiPb loops for WCLL BB of European DEMO11
Investigations on the microstructure evolution and mechanical properties of explosive welded ODS-Cu/316 L stainless steel composite11
Behavior of high-entropy W-rich alloys Wx(TaVCrTi)y under He+ irradiation11
Progress in preparing real-time control schemes for Deuterium-Tritium operation in JET11
Coils and power supplies design for the SMART tokamak11
Molecular dynamics simulations of the diffusion characteristics on the Fe-W interfaces system11
A design proposal for the European DEMO superconducting bus bars and current leads10
Plasma current measurement at JET using polarimetry-based fibre optic current sensor10
Development of Langmuir probe array for the new lower tungsten divertor in EAST10
Analysis of the thermal-hydraulic behavior of the EU-DEMO WCLL breeding blanket cooling systems during a loss of flow accident10
Evaluation of fatigue properties of reduced activation ferritic/martensitic steel, F82H for development of design criteria10
Current status of tokamak T-15MD10
Improvement of power quality in EAST power supply system based on hybrid active filter10
Membrane chemical exchange for lithium isotope enrichment(II): Multistage cascade process10
Mechanical and electromagnetic design of the vacuum vessel of the SMART tokamak10
Conceptual design overview of the ITER WCLL Water Cooling System and supporting thermal-hydraulic analysis10
A novel approach to the study of magnetohydrodynamic effect on tritium transport in WCLL breeding blanket of DEMO10
Electromagnetic analysis activities in support of the Breeding Blanket during the DEMO Pre-Conceptual Design Phase: Methodology and main results10
Computational design of magnetic beamlet deflection correction for NNBI10
Effect of temperature on the growth and surface bursting of He nano-bubbles in W under fusion-relevant He ion irradiations10
Numerical simulation of liquid metal MHD flows in a conducting rectangular duct with triangular strips10
CFD Investigation of helium gas flow in sphere packed (Pebble bed) in a rectangular canister using OpenFOAM10
Large scale experimental facility for performance assessment of the vacuum vessel pressure suppression system of ITER10
Dynamic simulation tools for isotopic separation system modeling and design10
Thermal-hydraulic modeling and analysis of the Water Cooling System for the ITER Test Blanket Module10
In-situ LIBS and NRA deuterium retention study in porous W-O and compact W coatings loaded by Magnum-PSI10
Lithium-lead corrosion behavior of zirconium oxide coating after heavy-ion irradiation10
Towards reliable design-by-analysis for divertor plasma facing components—Guidelines for inelastic assessment (part II: irradiated)10
Assessment of the chemical compatibility between EUROFER and ceramic breeder with respect to fatigue lifetime10
Exploration of power conversion thermodynamic cycles for ARC fusion reactor10
Parametric study of S-CO2 cycles for the DEMO fusion reactor10
Fusion technologies development at ENEA Brasimone Research Centre: Status and perspectives10
Structural, mechanical, electronic properties and Debye temperature of tungsten-technetium alloy: A first-principles study10
Structural assessment of the EU-DEMO WCLL Central Outboard Blanket segment under normal and off-normal operating conditions10
ECRH system upgrade design using dual frequency gyrotrons for EAST10
Extraction and separation of lithium isotopes by using organic liquid film extraction system of crown ether-ionic liquid10
Laser induced breakdown spectroscopy for hydrogen detection in molybdenum at atmospheric pressure mixtures of argon and nitrogen10
Research status of tungsten-based plasma-facing materials: A review10
Analysis of Test D1.1 of the LIFUS5/Mod3 facility for In-box LOCA in WCLL-BB10
Computational evaluation of N-16 measurements for a 14 MeV neutron irradiation of an ITER first wall component with water circuit10
High-heat flux tests of fusion materials with stationary plasma in the PLM device10
Analyses of the shielding options for HCPB DEMO blanket10
Towards large area CVD diamond disks for Brewster-angle windows10
CVD diamond photodetectors for FTU plasma diagnostics10
Thermal dynamic analyses of the primary heat transfer system for the WCCB blanket of CFETR10
Microstructure, mechanical and wear properties of friction stir processed Cu-1.0%Cr alloys10
Plasma current profile reconstruction for EAST based on Bayesian inference9
Impact of the plasma operation on the technical requirements in EU-DEMO9
Development and demonstration of a semi-automatic system for the bulk production of lithium titanate (Li2TiO3) pebbles by solid state reaction process (SSRP)9
First steps of the overall integration design of CFETR9
The engineering design of quarter size negative beam source for the comprehensive research facility for fusion technology9
Li2TiO3 pebble fabrication by freeze granulation & freeze drying method9
Investigation of atmospheric tritiated water vapor level around the Fukushima Daiichi nuclear power plant9
Fabrication of an ultrafine-grained W-ZrC-Re alloy with high thermal stability9
Advances in Additive Manufacturing of fusion materials9
0.033132076263428