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Geometrical properties of a “snowflake” divertor
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Fusion Nuclear Science Facilities and Pilot Plants Based on the Spherical Tokamak
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Bootstrap current in TFTR
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Generalized ripple-banana transport in a tokamak
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A survey of electron Bernstein wave heating and current drive potential for spherical tokamaks
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100 s extraction of negative ion beams by using actively temperature-controlled plasma grid
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High-Harmonic Fast-Wave Power Flow along Magnetic Field Lines in the Scrape-Off Layer of NSTX
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July 2012 |
Achievement and improvement of the JT-60U negative ion source for JT-60 Super Advanced (invited)
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Active feedback stabilization of axisymmetric modes in highly elongated tokamak plasmas
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Achievement of 500 keV negative ion beam acceleration on JT-60U negative-ion-based neutral beam injector
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PPPL ST-FNSF Engineering Design Details
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Design Details of the Transient CHI Plasma Start-up System on NSTX-U
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Chapter 2: Plasma confinement and transport
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Penetration of energetic neutral beams into fusion plasmas
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Design of the ITER PF Coils
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Increased divertor exhaust by electrical bias in DIII-D
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EBW simulation for MAST and NSTX experiments
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RADIO FREQUENCY POWER IN PLASMAS: 16th Topical Conference on Radio Frequency Power in Plasmas, AIP Conference Proceedings
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The toroidal field coil design for ARIES-ST
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Controlled Optimization of Mode Conversion from Electron Bernstein Waves to Extraordinary Mode in Magnetized Plasma
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ELMs and constraints on the H-mode pedestal: peeling–ballooning stability calculation and comparison with experiment
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Effects of divertor geometry on tokamak plasmas
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Conceptual design of a component test facility based on the spherical tokamak
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The H-mode pedestal, ELMs and TF ripple effects in JT-60U/JET dimensionless identity experiments
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Modeling divertor concepts for spherical tokamaks NSTX-U and ST-FNSF
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Ferritic insertion for reduction of toroidal magnetic field ripple on JT-60U
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Performance Boost in Industrial Multifilamentary Nb3Sn Wires due to Radiation Induced Pinning Centers
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Investigation of resistive wall mode stabilization physics in high-beta plasmas using applied non-axisymmetric fields in NSTX
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Cable-in-conduit conductors: lessons from the recent past for future developments with low and high temperature superconductors
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The EIRENE and B2-EIRENE Codes
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Theory of current drive in plasmas
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Ideal MHD stability limits of low aspect ratio tokamak plasmas
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Properties of Alfvén eigenmodes in the Toroidal Alfvén Eigenmode range on the National Spherical Torus Experiment-Upgrade
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Internal transport barriers in the National Spherical Torus Experiment
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Accounting of the power balance for neutral-beam heated H-mode plasmas in NSTX
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Fusion Nuclear Science Facilities and Pilot Plants Based on the Spherical Tokamak
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Heat deposition into the superconducting central column of a spherical tokamak fusion plant
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Toroidal ripple transport of beam ions in the mega-ampère spherical tokamak
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CQL3D-Hybrid-FOW modeling of the temporal dynamics of NSTX NBI+HHFW discharges
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RADIOFREQUENCY POWER IN PLASMAS: Proceedings of the 20th Topical Conference, AIP Conference Proceedings
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Plasma profile and shape optimization for the advanced tokamak power plant, ARIES-AT
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Resistive Wall Mode Instability at Intermediate Plasma Rotation
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Experimental investigation of transport phenomena in the scrape-off layer and divertor
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Inter-ELM Power Decay Length for JET and ASDEX Upgrade: Measurement and Comparison with Heuristic Drift-Based Model
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Nuclear performance assessment of ARIES-AT
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European Nb 3 Sn Superconducting Strand Production and Characterization for ITER TF Coil Conductor
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Progress in the physics basis of a Fusion Nuclear Science Facility based on the Advanced Tokamak concept
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The resistive wall mode and feedback control physics design in NSTX
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Performance Analysis of the ITER Poloidal Field Coil Conductors
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Disruption induced mechanical loads calculated with a coupled 3-D eddy current/2-D MHD plasma model
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Plasma formation in START and MAST spherical tokamaks
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Scaling of H-mode energy confinement with I p and B T in the MAST spherical tokamak
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Radiative Divertor Modelling for ITER and TPX
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Spectral effects on fast wave core heating and current drive
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Parametric dependence of fast-ion transport events on the National Spherical Torus Experiment
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Fusion materials science: Overview of challenges and recent progress
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May 2005 |
Development of Radiation Resistant Magnets for JHF/J-PARC
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June 2004 |
Analysis of a multi-machine database on divertor heat fluxes
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May 2012 |
MAST-upgrade divertor facility and assessing performance of long-legged divertors
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Confinement of High-Energy Trapped Particles in Tokamaks
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August 1981 |
Modifications to ideal stability by kinetic effects in NSTX
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October 2015 |
Sizing up plasmas using dimensionless parameters
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Collisionality and safety factor scalings of H-mode energy transport in the MAST spherical tokamak
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June 2011 |
Progress in understanding error-field physics in NSTX spherical torus plasmas
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Neutron irradiation damage in MgO, Al2O3 and MgAl2O4 ceramics
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Experimental vertical stability studies for ITER performance and design guidance
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Structural, thermal, electrical and magnetic properties of Eurofer 97 steel
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Bootstrap current scaling in tokamaks
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February 1992 |
Thermal fluid multiphysics optimization of spherical tokamak centerpost
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August 2012 |
Power and particle exhaust in an ST-FNSF
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conference
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June 2013 |
High harmonic fast waves in high beta plasmas
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November 1995 |
Development of radiation-resistant magnet coils for high-intensity beam lines
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July 1994 |
Numerical techniques used in Neutral Beam Injection modules
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The roles of plasma rotation and toroidal field ripple on the H-mode pedestal structure in JT-60U
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April 2006 |
Aspect ratio scaling of ideal no-wall stability limits in high bootstrap fraction tokamak plasmas
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February 2004 |
Design Description for a Coaxial Helicity Injection Plasma Start-Up System for a ST-FNSF
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October 2015 |
Scaling of Electron and Ion Transport in the High-Power Spherical Torus NSTX
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April 2007 |
Collisional Damping of Electron Bernstein Waves and its Mitigation by Evaporated Lithium Conditioning in Spherical-Tokamak Plasmas
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June 2009 |
Observation of Instability-Induced Current Redistribution in a Spherical-Torus Plasma
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Conceptual design study of the K-DEMO magnet system
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October 2015 |
Stability analysis of the vertical position control loop in TCV using rigid and deformable plasma models
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Progress in understanding the enhanced pedestal H-mode in NSTX
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The physics of production, acceleration and neutralization of large negative ion beams
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Super-X divertors and high power density fusion devices
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Stabilization of external modes in tokamaks by resistive walls and plasma rotation
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April 1994 |
Advances in high-harmonic fast wave physics in the National Spherical Torus Experiment
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May 2010 |
Characterization of a high-temperature superconducting conductor on round core cables in magnetic fields up to 20 T
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February 2013 |
High magnetic field generation using single-turn coils
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Design of a 40 megawatt homopolar generator
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Spherical torus concept as power plants—the ARIES-ST study
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Power requirement for accessing the H-mode in ITER
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A review of Non-Inductive current drive theory
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Solenoid-free plasma start-up in spherical tokamaks
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Density limits in toroidal plasmas
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Steady-state operation in compact tokamaks with copper coils
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A new look at density limits in tokamaks
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Enhanced ITER resistive wall mode feedback performance using optimal control techniques
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The super X divertor (SXD) and a compact fusion neutron source (CFNS)
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Modeling of active control of external magnetohydrodynamic instabilities
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Active Stabilization of the Resistive-Wall Mode in High-Beta, Low-Rotation Plasmas
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Materials R&D for a timely DEMO: Key findings and recommendations of the EU Roadmap Materials Assessment Group
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ARC: A compact, high-field, fusion nuclear science facility and demonstration power plant with demountable magnets
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An approximation to the critical commuting pair for breakup of noble tori
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The enhanced pedestal H-mode in the National Spherical Torus experiment
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Structural analysis of an optimally designed spherical tokamak centerpost
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Characterization of peeling–ballooning stability limits on the pedestal
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Advances in global MHD mode stabilization research on NSTX
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Status of the ITER heating neutral beam system
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ITER Central Solenoid design
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Resistive wall stabilized operation in rotating high beta NSTX plasmas
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On the physics guidelines for a tokamak DEMO
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Impact of MHD equilibrium input variations on the high beta stability boundaries of NSTX
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On heat loading, novel divertors, and fusion reactors
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July 2007 |
Physics Basis of a Fusion Development Facility Utilizing the Tokamak Approach
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Prospects for pilot plants based on the tokamak, spherical tokamak and stellarator
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August 2011 |
Fast-wave power flow along SOL field lines in NSTX and the associated power deposition profile across the SOL in front of the antenna
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Effect of Collisionality on Kinetic Stability of the Resistive Wall Mode
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February 2011 |
High harmonic fast wave heating efficiency enhancement and current drive at longer wavelength on the National Spherical Torus Experiment
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The effect of trapped electrons on beam driven currents in toroidal plasmas
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April 1980 |
Resistive wall mode stabilization of high-β plasmas in the National Spherical Torus Experiment
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Non-inductive current generation in NSTX using coaxial helicity injection
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Diffusion Driven Plasma Currents and Bootstrap Tokamak
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A Novel superconducting toroidal field magnet concept using advanced materials
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2009 Joint 48th IEEE Conference on Decision and Control (CDC) and 28th Chinese Control Conference (CCC), Proceedings of the 48h IEEE Conference on Decision and Control (CDC) held jointly with 2009 28th Chinese Control Conference
https://doi.org/10.1109/CDC.2009.5400543
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Multimodal options for materials research to advance the basis for fusion energy in the ITER era
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Conceptual Design of ITER In-Vessel Vertical Stabilization Coil Power Supply System
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journal
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June 2014 |
Suitability of coated conductors for fusion magnets in view of their radiation response
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December 2014 |
Beta-limiting instabilities and global mode stabilization in the National Spherical Torus Experiment
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May 2002 |
Plasma Edge Physics with B2-Eirene
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journal
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February 2006 |
Physics aspects of negative ion sources
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journal
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May 2006 |
Tritium supply assessment for ITER and DEMOnstration power plant
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October 2013 |
Dynamical evolution of pedestal parameters in ELMy H-mode in the National Spherical Torus Experiment
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journal
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September 2011 |
Toroidal reactor designs as a function of aspect ratio and elongation
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journal
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May 2002 |
High-harmonic fast magnetosonic wave coupling, propagation, and heating in a spherical torus plasma
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journal
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May 1999 |
Remote Handling and Plasma Conditions to Enable Fusion Nuclear Science R&D Using a Component Testing Facility
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journal
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August 2009 |
Triggered Confinement Enhancement and Pedestal Expansion in High-Confinement-Mode Discharges in the National Spherical Torus Experiment
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journal
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September 2010 |
Fusion–Fission Transmutation Scheme—Efficient destruction of nuclear waste
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January 2009 |
Plasma equilibrium reconstructions in the lithium tokamak experiment
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May 2012 |
HTS twisted stacked-tape cable conductor
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A component test facility based on the spherical tokamak
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Stability Analysis of Resistive Wall Kink Modes in Rotating Plasmas
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Long pulse neutral beam injection
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Attaining neoclassical transport in ignited tokamaks
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Evaluation of copper alloys for fusion reactor divertor and first wall components
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Numerical Transport Codes
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Neutron irradiation effects on superconducting wires and insulating materials
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ARIES-ST nuclear analysis and shield design
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The physics of tokamak start-up
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SlimCS—compact low aspect ratio DEMO reactor with reduced-size central solenoid
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Design study for 20 T 15 cm bore hybrid magnet with radiation-resistant insert for pion capture
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conference
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Mission and Readiness Assessment for Fusion Nuclear Facilities
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Neutronics design of the low aspect ratio tokamak reactor, VECTOR
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The tokamak Monte Carlo fast ion module NUBEAM in the National Transport Code Collaboration library
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Toroidal self-consistent modeling of drift kinetic effects on the resistive wall mode
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journal
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November 2008 |
Progress in characterization of the pedestal stability and turbulence during the edge-localized-mode cycle on National Spherical Torus Experiment
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journal
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Effects of Neutron Irradiation on the Critical Temperature and Critical Current of Nb-Tube Processed Nb3Al Multifilamentary Wires. [Nbチューブ法Nb3Al極細多芯線の臨界温度および臨界電流に及ぼす中性子照射効果]
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Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan, Vol. 37, Issue 7
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Structural materials for fission & fusion energy
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Improved magnetohydrodynamic stability through optimization of higher order moments in cross-section shape of tokamaks
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TPX Neutral Beam injection system design
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Resistive magnet technology for hybrid inserts
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Momentum transport in electron-dominated NSTX spherical torus plasmas
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Plasma modelling results and shape control improvements for NSTX
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November 2011 |
Overview of the physics and engineering design of NSTX upgrade
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Heuristic drift-based model of the power scrape-off width in low-gas-puff H-mode tokamaks
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Electromechanical analysis of a prototype 20 Tesla, single turn toroidal field coil for IGNITEX
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Scaling of the tokamak near the scrape-off layer H-mode power width and implications for ITER
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Snowflake divertor configuration studies in National Spherical Torus Experiment
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August 2012 |
Nuclear Aspects and Blanket Testing/Development Strategy for ST-FNSF
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May 2014 |
The role of kinetic effects, including plasma rotation and energetic particles, in resistive wall mode stability
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August 2010 |
Fusion Nuclear Science Facility (FNSF)
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Development of a negative ion-based neutral beam injector in Novosibirsk
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Efficient generation of noninductive, off-axis, Ohkawa current, driven by electron Bernstein waves in high β, spherical torus plasmas
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Magnetic drift kinetic damping of the resistive wall mode in large aspect ratio tokamaks
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Radiation effect on interlaminar shear strength of the electric insulation system with cyanate ester and epoxy blended resin
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ADVANCES IN CRYOGENIC ENGINEERING: Transactions of the International Cryogenic Materials Conference - ICMC, Volume 58, AIP Conference Proceedings
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Radiation resistance of fusion magnet materials
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'Natural elongation' of spherical tokamaks
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Progress towards steady state at low aspect ratio on the National Spherical Torus Experiment (NSTX)
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Unified Ideal Stability Limits for Advanced Tokamak and Spherical Torus Plasmas
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Exploration of the equilibrium operating space for NSTX-Upgrade
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Disruptions, disruptivity and safer operating windows in the high- β spherical torus NSTX
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April 2013 |
Application of dimensionless parameter scaling techniques to the design and interpretation of magnetic fusion experiments
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March 2008 |
Profiles of fast ions that are accelerated by high harmonic fast waves in the National Spherical Torus Experiment
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journal
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Calculation of the non-inductive current profile in high-performance NSTX plasmas
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journal
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February 2011 |
Progress toward commissioning and plasma operation in NSTX-U
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Conceptual design study of a superconducting spherical tokamak reactor with a self-consistent system analysis code
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October 2011 |
Conceptual design study of the moderate size superconducting spherical tokamak power plant
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May 2015 |
Electro-mechanical properties of REBCO coated conductors from various industrial manufacturers at 77 K, self-field and 4.2 K, 19 T
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