Fusion Science and Technology

Papers
(The median citation count of Fusion Science and Technology is 0. 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
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
A Software Package for Plasma-Facing Component Analysis and Design: The Heat Flux Engineering Analysis Toolkit (HEAT)10
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
Technology Development for Isotope Rebalancing and Protium Removal in the EU-DEMO Fuel Cycle9
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
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
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
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
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
Automatic Recognition of Anomalous Patterns in Discharges by Applying Deep Learning3
FERMI: Fusion Energy Reactor Models Integrator3
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
Multidimensional Modeling of Steam-Methane-Reforming-Based Fuel Processor for Hydrogen Production2
Adsorption Study of Main Gas Products from Water Radiolysis on 4A Zeolite by Numerical Simulations2
The Development and Testing of a Digital ITER-Type Mock-Up Based on Virtual Reality Technology2
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
Comparison of Shadowgraphy and X-Ray Phase Contrast Methods for Characterizing a DT Ice Layer in an Inertial Confinement Fusion Target2
A Fusion Reactor Scheme Using Magnetic Mirrors2
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
Tritium-Related Activities in the Russian Federation2
Concept Design and Analysis of the Magnet System of the Sustained High Power Density Tokamak Facility2
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
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
Computational Assessment on Impurity Sourcing and Transport Using High-Temperature Graphite and Silicon Carbide Plasma-Facing Walls in a Tokamak Environment2
Activation Analysis and Evaluation of Radionuclide Inventory Decay Heat for EU DEMO Vacuum Vessel Components2
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
A Numerical Simulation for Fusion Reaction in Tokamak D-T Plasma2
Comparison of Hydrogen Isotope Retention in Divertor Tiles of JET with the ITER-Like Wall Following Campaigns in 2011–2012 and 2015–20162
The Impact of Disruptions on the Economics of a Tokamak Power Plant2
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
Updated Thermofluid Performance of the Simplified Flat Variant of the HEMJ1
Numerical Simulation Analysis of Flow Field on Repetitive Pellet Injector with Single-Screw Extruder in CFETR1
Tritium Behavior in Water and Gas Produced by a Fully Tritium-Compatible Electrolyzer1
Tritium Effects on Aromatic Carbon–Loaded Polymers1
Benchmarking Hydrogen Isotope Separation Efficiency of Pd/k–Packed TCAP Columns1
Screening the Optimal Loading of a Pt-Catalyzed Zeolite for Hydrogen Isotope Exchange1
Experiments on the MHD Effect on the Drainage of a LiPb Channel and Supporting Numerical Computations with the Level Set Method1
Experimental Investigation of CECE Process to Recover Tritium and Deuterium from Low Tritiated/Deuterated Liquid Waste1
Edge Toroidal Rotation Analysis by CXRS Diagnostic on EAST1
Energy Confinement Dynamics and Some Properties of Plasma Self-Organization in ECRH Regime in the L-2M Stellarator1
Bayesian Parameter Estimation of the k -ω Shear Stress Transport Model for Accurate Simulations of Impinging-Jet Heat Transfer1
Determination of the Oxygen Concentration in GDP Thin Films Using Rutherford Backscattering Spectroscopy1
Thermo-Mechanical Distortion of Tungsten-Coated Steel During High Heat Flux Testing Using Plasma Arc Lamps1
What Would Happen to a Fusion Power Plant in the Case of Plasma Disruption? A Dynamic Model Simulation1
Neutronic Analysis of the Fusion Reactor ARC: Monte Carlo Simulations with the Serpent Code1
Measurement of Palladium Hydride and Palladium Deuteride Isotherms Between 130 K and 393 K1
Study on CH4 Oxidation and H2O Adsorption for Hydrogen Isotope Recovery1
UNITY: Kyoto Fusioneering’s Unique Integrated Testing Facility for Fusion Power Generation1
Self-Controlled Flashing Nuclear Fusion in Stationary Magnetized Low-Temperature Plasma1
Neutronics Modeling and Nuclear Analysis Based on the Full CAD Geometry of CFETR1
Performance Restoration of a Tritium-Aged LaNi4.25Al0.75 Sample1
Strategical Approach for the Neutronics in the European Fusion Programme1
Effect of Welding Speed and Postweld Heat Treatment on Microstructural Characterization and Mechanical Properties of Gas Tungsten Arc Welded Ti-15V-3Al-3Cr-3Sn Joints1
Temporal Profiling of Electron Temperatures Using the Hα–Hβ Line Emission and Triple Langmuir Probe Array in the Pre-Ionization Discharge of the MT-I Spherical Tokamak1
Inhibition Effect of CO on Hydrogen Permeation Through a Pd/Al2O3 Composite Membrane: A Comprehensive Study on Concentration Polarization and Competitive Adsorption Effect1
Alfvén-Sound Eigenmode Modeling in GLOBUS-M Tokamak1
Comprehensive Analysis of Streaming and Shutdown Dose Rate Experiments at JET with ORNL Fusion Neutronics Workflows1
Organic Vacuum Pump Fluids for the Vacuum Pumping of Fusion Power Plants1
Readout Electronics for Fast Neutron Flux Measurement with High Time Resolution on HL-2M Tokamak1
A Thin Alumina Film as a Tritium Adsorption Inhibitor for Stainless Steel 3161
Shear Strength and Release of Large Cryogenic Pellets from the Barrel of a Shattered Pellet Injector for Disruption Mitigation1
Research of the Characteristics of Semiconductor Bridge (SCB) Plasma1
Pressure Response Optimization of an Eddy Current-Driven Flyer Plate Valve for the ITER Shattered Pellet Injection System1
Progress of Engineering Design of CFETR Machine Assembly1
Design and Analysis of an Advanced Three-Point Bend Test Approach for Miniature Irradiated Disk Specimens1
Parameter Space Constraints for Compact Spherical Tokamak Fusion Reactors1
Improving the Charge Preamplifier of ITER Neutron Flux Monitor System1
A Study on Interactions of 14.7-MeV Protons and 3.6-MeV Alphas in 93 Nb Target1
Effect of the Fusion Fuels’ Polarization on Neutron Wall Loading Distribution in CFETR1
MEPhIST-0 Tokamak for Education and Research1
Neutronics Calculations to Support the Fusion Evaluated Nuclear Data Library (FENDL)1
Investigation of Pressure Drop Calculation for Twisted Tape Swirl Tubes by Conventional Channel Flow Correlations with Fusion Applications1
Benchmark Experiments for Verification of Nuclear Data Libraries for Designing Fusion Blankets1
Conservative Tritium Exposure Assessment in the Atmosphere from the Spray Ponds of the Balakovo NPP1
Separatrix-to-Wall Simulations of Impurity Transport with a Fully Three-Dimensional Wall in DIII-D1
Multiscenario Electromagnetic Load Analysis of Blanket and VV for CFETR1
Theoretical Study of the Impedance Matching of the Ferrite Tuner System for ICRF Heating1
Design, Fabrication, and Test of a Prototype of Matrix Heat Exchanger for Cryogenic Distillation of Hydrogen Isotopes1
Performance Comparison of Helium and sCO 2 as Coolants for Modular Finger-Type Divertors1
The Radiation Impact of Delayed Photoneutron Production in ITER Components1
Final Design of Vacuum Pumping Systems for the Material Plasma Exposure eXperiment1
Indigenous Development of Epoxy Resin System for Cryogenic Services and Fusion Application1
Power Quality Analysis for Poloidal Field Power Supply System in EAST1
MHD Simulation of Hemisphere Plasma Focus Using Snowplow Model1
Thermogravimetric Oxidation Analyses of Carbon Tokamak Codeposits and Flakes1
Numerical Calculations of Liquid-Metal Magnetohydrodynamic Flows Through Circular Pipe in Magnetic Field Inlet Region and Outlet Region1
Heat Transport Augmentation Using Vibration Material Excited by Boiling Bubbles for Heat Removal from Divertor1
Conceptual Design of Control System for the Prototype RF-Driven Negative Ion Source at ASIPP1
Radiation and Nuclear Physics Aspects of the Use of the Thorium Fuel Cycle in a Hybrid Fusion Facility1
Overview of Liquid-Metal PFC R&D at the University of Illinois Urbana-Champaign1
Choice of Gas Isotope Composition for Neutral Beam Injectors of the FNS-ST Compact Fusion Neutron Source1
A Forward Analytic Model of Neutron Time-of-Flight Signals for Inferring Ion Temperatures from MagLIF Experiments1
Construction of Data Acquisition and Processing System for Diagnostics Based on TSN Fiber Network at ASIPP NBI System1
Application of Pt-Loaded Honeycomb Catalysts in Air Detritiation1
Scoping Nuclear Analyses of Shielding Options and Shutdown Dose Rate Contributions in ITER TBSs1
CHIMERA Fusion Technology Facility: Testing and Virtual Qualification1
Heat Transfer Performance of Cu-Cr-Zr Tube with Swirl Insert Under Cyclic Thermal Loading in Monoblock Divertor1
Uranium Bed Design Parameters for Tritium Plants Supporting Fusion Reactors1
Cross Comparisons of X-Ray Imaging Crystal Spectrometer and Charge Exchange Spectroscopy from KSTAR1
Large Component Simulation of an Inboard Sector of a Dual-Coolant Lead-Lithium Blanket1
Characterization of Doping Distribution of ICF Capsules by X-Ray Tomography1
Development of a High Heat Flux Electric Joule Heating System for Testing a One-Side Heated Cooling Channel1
Thoughts on the H-Bomb Decision, Oppenheimer’s Loyalty/Security Hearing, and Vacating of the AEC Decision0
Determination of Electron Temperature of Pulsed Washer Gun–Generated Argon Plasma by Corona Model0
Thermohydraulic Design Analysis of the Target Assembly in the Material Plasma Exposure eXperiment Facility0
Microscopic Corrosion Process and Electrochemical Properties of JLF-1 Steel (Fe-9Cr-2W) in the Molten Salt LiF-NaF-KF0
Optical System Design for Laser-Induced Fluorescence Study of Helium Atoms on the Linear Plasma Device0
Investigations of Microstructure and Mechanical Properties of Post-Weld Heat-Treated DP780 Steel TIG Welds0
Proof-of-Concept Modeling for the Use of Neutron Reflectometry for the In-Situ Diagnosis of Deuterium Accumulation in Tungsten and Dispersion-Strengthened Tungsten Alloys0
Radiation Damage Analysis of FNSF Components Using McCad and MCNP0
Speed of Sound Measurement of Hydrogen Isotopologues Containing Tritium for Reference Gas Sample Verification0
Confirmation of the Absence of Contact Between Edge Boundary Plasma and Inboard First Wall in LHD Discharges Based on Radial Profile Measurement of Hβ Line Emissions0
Modeling the Tokamak Exhaust Processing System in a Commercial Simulator for Process Monitoring Purposes0
Experimental Study on Mechanical Characteristics of Li2TiO3 Pebble Beds Under Cyclic Loading0
Preliminary Neutronics Study of an Accelerator-Driven Molten Spallation Target–Molten Lithium Source of Tritium0
Design and Manufacturing of a High-Efficiency Microreactor in View of Converting Tritiated Streams to Water0
Numerical Simulation of Airflow and Dust Migration in Vacuum Vessel During Loss of Vacuum Accident for Updated CFETR0
Determination of the Surface-Rate Coefficients of Deuterium Through Nickel by Gas-Driven Permeation Experiments in Surface-Limited Regime0
Effect of Positive Polarity in an Inertial Electrostatic Confinement Fusion Device: Electron Confinement, X-Ray Production, and Radiography0
Possibilities of Reprocessing Solid Waste with Tritium from Fusion Using High-Temperature Heating0
Numerical Comparison of Dehydriding Behaviors of Full-Scale Depleted Uranium Beds Equipped with Copper Foam or Copper Fins0
NMR Spectroscopy for Proof-of-Concept Experimentation on a Polarized Laser Fusion Process0
A Safer, Smaller, Cleaner Subcritical Thorium Fission—Muonic Fusion Hybrid Reactor0
Deuterium Stream Management Leaving the LPCE Column in a CECE Process for Heavy Water Detritiation0
Design and Development of 0.3-T Toroidal Field Coil System for Small-Sized MT-II Spherical Tokamak0
Organically Bound Tritium Activity Level in Plants During Growing Season and Environmental Factor Influences0
Influence of Microstructure on the Absorption of Tritium into Gold-Plated 316 Stainless Steel0
Likely U.S. Regulatory Considerations for D-T Fusion Power Reactors0
Neutron Direction Distribution in D-T Plasma0
Experimental Estimation of Dust Generation Under ELM-Like Transient Heat Loads in Divertor Plasma Simulator-20
Parametric Studies of CCRF in Ar on 1D Model: Effect of Pressure and Dielectric Layers0
A Plasma Window–Enhanced Accelerator-Based Deuterium-Tritium Neutron Generator System0
Special issue featuring Young Investigators in Fusion0
Performance of W-1%Y2O3-0.5%Ti Plasma-Facing Composite Under Fusion Relevant Transient Heat Flux0
Review of Recent Progress in Plasma-Facing Material Joints and Composites in the FRONTIER U.S.-Japan Collaboration0
Instrumentation and Control for Tritium Compatible Hydrogen Generator0
Structural Design for ITER Gas Injection System Gas Fueling Gas Valve Box0
Three-Dimensional Electromagnetic and Structural Analysis of Disruptions in the COMPASS Upgrade Vacuum Vessel0
A Nodal Model for Tokamak Burning Plasma Space-Time Dynamics0
Improved Glow Discharge Polymer Removal from Beryllium Capsules Using Ozone0
ORNL Progress in Disruption Mitigation Technology in Support of ITER0
Erosion of Fuzz Layers Formed in Steady-State Plasma Discharge0
Thermodynamics and Kinetics Analysis of Hydrogen Absorption by Zr 0.8 Ti 0.2 Co Alloy0
Atomistic Study on the Energetic and Mechanical Behaviors of Helium Bubble Nucleation and Growth in RAFM Steel0
Initial Commissioning Test Results of the Wendelstein 7-X Continuous Pellet Fueling System0
Experimental and Numerical Evaluation of the Thermal-Fluid Characteristics of the Helium-Cooled Modular Divertor with Multiple Jets Using a Reversed Heat Flux Approach0
Occupational Radiation Exposure Estimated for Fusion Demonstration Reactors and Beyond0
Conceptual Neutronics Study of a Hybrid Fusion Neutron Source FNS-C with Aqueous Blanket0
Simulated Aging of Metal Tritides by Ball Milling Induced Gas Incorporation0
Generation and Analysis of Tritium-Substituted Methane0
Internal Kink Instabilities Driven by Poloidal Flow via Non-Resonant Excitation in Tokamaks0
NSTX-U Personnel Safety System: Safety Instrumented System Development and Design0
Polishing and Local Planarization High-Precision HDC Capsules by Four-Cup-Type Technology for Inertial Confinement Fusion0
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