Fusion Science and Technology

Papers
(The TQCC of Fusion Science and Technology is 2. The table below lists those papers that are above that threshold based on CrossRef citation counts [max. 250 papers]. The publications cover those that have been published in the past four years, i.e., from 2020-03-01 to 2024-03-01.)
ArticleCitations
Progress Toward Interpretable Machine Learning–Based Disruption Predictors Across Tokamaks25
Estimation and Uncertainties of Profiles and Equilibria for Fusion Modeling Codes24
Hydrogen Isotope Dissolution and Release Behavior of Rare Earth Oxides21
Fusion–Fission Hybrid Systems: Yesterday, Today, and Tomorrow19
Discussions on Tritiated Water Treatment for Fukushima Daiichi Nuclear Power Station18
Code-to-Code Comparison for a PbLi Mixed-Convection MHD Flow15
Grad-Shafranov Equation in Fractal Dimensions14
Design of Higher-Order Circular Array Antenna with Multiple Patch Elements Based on Angular Momentum13
Targeting a Versatile Actuator for EU-DEMO: Xenon Doping of Fueling Pellets12
Research Facilities of IAE NNC RK (Kurchatov) for Investigations of Tritium Interaction with Structural Materials of Fusion Reactors12
Cost Drivers for a Tokamak-Based Compact Pilot Plant11
A Software Package for Plasma-Facing Component Analysis and Design: The Heat Flux Engineering Analysis Toolkit (HEAT)10
Application of High-Energy Tritium Ions and Alpha Particles Formed in 6Li(n,α)T Nuclear Reaction to Excite the Luminescence of Inert Gas Mixtures10
Technology Development for Isotope Rebalancing and Protium Removal in the EU-DEMO Fuel Cycle9
Preliminary Experimental Results of Shattered Pellet Injection on the HL-2A Tokamak9
The Study of CECE Process for Low-Tritiated Liquid Waste Prior to Experimental Phase9
Shatter Thresholds and Fragment Size Distributions of Deuterium–Neon Mixture Cryogenic Pellets for Tokamak Thermal Mitigation9
Code Integration, Data Verification, and Models Validation Using the ITER Integrated Modeling and Analysis System (IMAS) in EUROfusion8
Detection of Alfvén Eigenmodes on COMPASS with Generative Neural Networks8
Impact of High-Power Heat Load and W Surface Carbidization on Its Structural-Phase Composition and Properties8
Thermophysical Parameter Estimation of a Neutron Source Based on the Action of Broadband Radiation on a Cylindrical Target8
Overview of the Tritium Technologies for the EU DEMO Breeding Blanket8
Deep Learning for the Analysis of Disruption Precursors Based on Plasma Tomography7
Architecture of Fuel Systems of Hybrid Facility DEMO-FNS and Algorithms for Calculation of Fuel Flows in the FC-FNS Model7
Precipitate Size in GRCop-84 Gas Atomized Powder and Laser Powder Bed Fusion Additively Manufactured Material7
Matter Injection in EU-DEMO: The Preconceptual Design7
Tritium Processing Systems and First Tritium Operation of the KATRIN Experiment7
Targeting a Versatile Actuator for EU-DEMO: Novel Control Scheme for Multisource Pellet Injector6
The Source Permeator System and Tritium Transport in the TEX PbLi Loop6
Material Characterization of Hierarchical Tunable Pore Size Polymer Foams Used in the MARBLE Mix Morphology Experiment6
Machine Learning Algorithms for Automated NIF Capsule Mandrel Selection6
Prospects for Disruption Handling in a Tokamak-Based Fusion Reactor6
A First Generation Fusion Reactor Using the D-3He Cycle6
Tritium Supply and Processing for the First KATRIN Tritium Operation6
A Study of the Requirements of p-11B Fusion Reactor by Tokamak System Code6
Spent Nuclear Fuel Incineration by Fusion-Driven Liquid Transmutator Operated in Real Time by Laser6
The Design and Manufacturing of HL-2M Vacuum Vessel6
Diffusion Characterization of Hydrogen Isotopes in Hastelloy N Alloy for the Application of Fluoride-Salt-Cooled High-Temperature Reactors (FHRs)6
Numerical Calculations on Liquid-Metal Magnetohydrodynamic Flow in Magnetic Field Inlet Region and Outlet Region5
The Current Status of the Heavy Water Detritiation Facility at the NRC (Kurchatov Institute) – PNPI5
Tritium Research and Development Status at KAERI5
Conceptual Design for a Blanket Tritium Extraction Test Stand5
Evaluation of Alpha Particle Emission Rate Due to the p-11B Fusion Reaction in the Large Helical Device5
A Hard X-Ray Pinhole Camera System for Fast Electron Bremsstrahlung Measurements in the HL-2A Tokamak5
Permeator Simulations for the EU-DEMO Fuel Cycle5
Study of Electrolyzer Materials at High Tritium Concentrations5
Analysis of the Shattered Pellet Injection Fragment Plumes Generated by Machine Specific Shatter Tube Designs5
Tritium Permeation through Ce-ODS Steel5
Multiphysics Simulations of a Steady-State Lower Hybrid Current Drive Antenna for the FSNF5
Numerical Simulation of Thin-Film MHD Flow for Nonuniform Conductivity Walls5
Two-Gaussian Fitting Method for Charge Exchange Spectroscopy on Measurements of Ion Temperature and Toroidal Plasma Flow Velocity in the KSTAR Tokamak5
Effects of Helium Seeding on Deuterium Retention in Neutron-Irradiated Tungsten5
Actuator Development Step by Step: Pellet Particle Flux Control for Single- and Multiple-Source Systems5
Experimental Investigation of Thermal Properties of Materials Used to Develop Cryopump4
Development of New Magnetron Sputter Deposition Processes for Laser Target Fabrication4
Preliminary Accident Analysis of Ex-Vessel LOCA for the European DEMO HCPB Blanket Concept4
Synthesis, Characterization, and Hydrogen Isotope Storage Properties of Zr1-xTixCo and Zr1-xHfxCo Alloys (x = 0.1, 0.2)4
Tools for Image Analysis and First Wall Protection at W7-X4
Compatibility of FeCrAlMo in Flowing Pb-Li at 600°C to 700°C4
Issues in Formation of Cryogenic Pellets for Fusion Applications4
A Preliminary CFD and Tritium Transport Analysis for ARC Blanket4
Automatic Recognition of Anomalous Patterns in Discharges by Applying Deep Learning3
FERMI: Fusion Energy Reactor Models Integrator3
Advanced Isotope Separation Technology for Fusion Fuel3
Monitoring and Recovery of Tritium in a Fusion Test Facility3
R&D Activities for Fusion DEMO in the QST Rokkasho Fusion Institute3
Preliminary Safety Analysis of Tritium Source Term for the CFETR Tritium Plant3
Advanced Tools for ITER Tritium Plant System Modeling and Design3
Development of Stochastic Voronoi Lattice Structures via Two-Photon Polymerization3
Operational Tritium Inventories in the EU-DEMO Fuel Cycle3
The Compactness and Inboard Radial Build of Fusion Nuclear Devices3
Fusion Gain and Triple Product for the Sheared-Flow-Stabilized Z Pinch3
Precipitate Size in GRCop-42 and GRCop-84 Cu-Cr-Nb Alloy Gas Atomized Powder and L-PBF Additive Manufactured Material3
Analysis of the Reactor Experiment Results on Irradiation of Lead-Lithium Eutectic3
Estimation of Power Transmission of Fast Wave in ICRF Range Through Tokamak Plasma Edge with the Help of Reflection Coefficient3
Modeling of Transport Processes in Liquid-Metal Fusion Blankets: Past, Present, and Future3
Material Studies to Reduce the Tritium Memory Effect in BIXS Analytic Systems3
Development of Tritium Tracer Doped Liquid Fuel Target for Inertial Confinement Fusion at the Gekko XII-LFEX Facility3
A Review of Pellet Injector Technology: Brief History and Recent Key Developments3
Status and Progress of Liquid Metal Thermofluids Modeling for the U.S. Fusion Nuclear Science Facility3
The LIBRA Experiment: Investigating Robust Tritium Accountancy in Molten FLiBe Exposed to a D-T Fusion Neutron Spectrum3
Effect of 14.7-MeV Protons and 3.6-MeV Alpha Particles on Fusion Structural Materials3
Scale-Up Effects of Depleted Uranium (DU) Beds for Hydrogen Isotopes Storage3
Analysis of Design Alternatives of Actively Cooled RF Window for MPEX2
Specific Features and Current Status of Processes for Tritium Removal from Water: A Critical Review2
Plasma Diagnostics on Pulse Plasma-Focus Generators and Their Features as Alternative Fusion Reactors2
Hydrogen Transport in Tungsten for Nuclear Energy Application: Temperature Dependence and Compensation Effect2
Activation Analysis and Evaluation of Radionuclide Inventory Decay Heat for EU DEMO Vacuum Vessel Components2
Computational Assessment on Impurity Sourcing and Transport Using High-Temperature Graphite and Silicon Carbide Plasma-Facing Walls in a Tokamak Environment2
Neutronics Design of Fusion Reactor–Based Boron Neutron Capture Therapy in ITER2
Managing Fusion Radioactive Materials: Approaches and Challenges Facing Fusion in the 21st Century2
Tritium Distribution in the Low-Level and Intermediate-Level Wastes of a Korean CANDU Reactor2
Fundamental Analysis for Electrochemical Extraction and Monitoring of Impurities from Lead Lithium and Lithium with Chloride Molten Salt2
Comparison of Measurement Reliability of Nanosecond Rectangular Voltage Pulses by Kerr Effect and by High-Speed Voltage Probe2
Multidimensional Modeling of Steam-Methane-Reforming-Based Fuel Processor for Hydrogen Production2
Comparison of Hydrogen Isotope Retention in Divertor Tiles of JET with the ITER-Like Wall Following Campaigns in 2011–2012 and 2015–20162
The Development and Testing of a Digital ITER-Type Mock-Up Based on Virtual Reality Technology2
Monte Carlo Analysis of the Performance of the ITER Diagnostic Residual Gas Analyzer2
Design of a Cryostat for Spectroscopic Investigation of All Hydrogen Isotopologues in the Solid, Liquid, and Gaseous Phases2
Improved Plasma Vertical Position Control on TCV Using Model-Based Optimized Controller Synthesis2
Tritium Transport and Distribution in a High-Temperature Gas-Cooled Reactor2
Reconfiguration of an Electrothermal-Arc Plasma Source for In Situ PMI Studies2
An Integrated Design Study for an Advanced Tokamak to Close Physics Gaps in Energy Confinement and Power Exhaust2
Engineering Paradigms for Sheared-Flow-Stabilized Z-Pinch Fusion Energy2
Tritium Aging Effects on Fracture Toughness of Stainless Steel Weldments2
Detritiation of the Electrostatic Spectrometer of Troitsk Nu-mass Experiment2
Ultrathick Boron Carbide Coatings for Nuclear Fusion Targets2
FNSF Structural Sizing Studies2
Nature-Inspired Concepts for High-Power Electric Propulsion Systems2
Concept Design and Analysis of the Magnet System of the Sustained High Power Density Tokamak Facility2
Adsorption Study of Main Gas Products from Water Radiolysis on 4A Zeolite by Numerical Simulations2
Modeling Magnetic Material Using Vector Potential-Based Elements in ANSYS and Comparing with Edge-Based Elements2
Gaussian Process Tomography at ASDEX Upgrade with Magnetic Equilibrium Information and Nonstationary Kernels2
Seismic Analysis of the Vacuum Vessel for CFETR2
A Framework for International Collaboration on ITER Using Large-Scale Data Transfer to Enable Near-Real-Time Analysis2
A Fusion Reactor Scheme Using Magnetic Mirrors2
Comparison of Shadowgraphy and X-Ray Phase Contrast Methods for Characterizing a DT Ice Layer in an Inertial Confinement Fusion Target2
Applicability of a 100-mL Polyethylene Vial for Low-Level Tritium Measurement Using a Low-Background Liquid Scintillation Counter2
Summary of Tritium Source Term Study in 10 MW High Temperature Gas-Cooled Test Reactor2
Design and Verification of Calorimeter for CFETR Neutral Beam Injection System Prototype with Negative Ion Source2
CFD Simulation of Helium Flow Loop Test Section2
Examination of Early-Stage Helium Retention and Release in Dispersion-Strengthened Tungsten Alloys2
A Numerical Simulation for Fusion Reaction in Tokamak D-T Plasma2
Tritium-Related Activities in the Russian Federation2
The Impact of Disruptions on the Economics of a Tokamak Power Plant2
Effect of Hypervapotron Fin Angle on Subcooled Flow Boiling Heat Transfer Performance Under One-Side High-Heat Load Condition2
Final Design of the Material Plasma Exposure eXperiment2
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