| Paper | First Author | Title |
|---|
| FTP/P6-01 | Azizov, E. | Status of Project of Engineering-Physical Tokamak |
| FTP/P6-02 | Goto, T. | Importance of Helical Pitch Parameter in LHD-Type Heliotron Reactor Designs |
| FTP/P6-03 | Hwang, Y.S. | Conceptual Design Study of Superconducting Spherical Tokamak Reactor with a Self-Consistent System Analysis Code |
| FTP/P6-04 | Kamada, Y. | Research Regimes and Design Optimization of JT-60SA Device towards ITER and DEMO |
| FTP/P6-05 | Na, H.K. | Current Status and Facility Operation for the Third KSTAR Campaign |
| FTP/P6-06 | Neilson, G.H. | Progress toward Attractive Stellarators |
| FTP/P6-07 | Simonen, T.C. | A DT Neutron Source for Fusion Materials Development |
| FTP/P6-08 | Tazhibayeva, I. | Tokamak KTM Progress Activity for Preparation on First Plasma Start-up |
| FTP/P6-09 | Yang, H.L. | Status and Result of the KSTAR Upgrade for the 2010's Campaign |
| FTP/P6-10 | Kuteev, B.V. | Key Physics Issues of a Compact Tokamak Fusion Neutron Source |
| FTP/P6-11 | Giruzzi, G. | Objectives, Physics Requirements and Conceptual Design of an ECRH System for JET |
| FTP/P6-12 | Imai, T. | Development of Over-1 MW Gyrotrons for the LHD and the GAMMA 10 ECH Systems |
| FTP/P6-13 | Kobayashi, T. | Progress of High Power and Long Pulse ECRF System Development in JT-60 |
| FTP/P6-14 | Shiraiwa, S. | Design and Commissioning of a Novel LHCD Launcher on Alcator C-Mod |
| FTP/P6-15 | Takase, Y. | Development of a Plasma Current Ramp-up Technique for Spherical Tokamaks by the Lower-Hybrid Wave |
| FTP/P6-16 | Bae, Y.S. | Commissioning Results of the KSTAR Neutral Beam System |
| FTP/P6-17 | Hiwatari, R. | Plasma Commissioning Scenario and Initial Tritium Inventory for Demo-CREST |
| FTP/P6-18 | Konishi, S. | Fusion-Biomass Hybrid Concept and its Implication in Fusion Development |
| FTP/P6-19 | Mitarai, O. | The High Density Ignition in FFHR Helical Reactor by Neutral Beam Injection (NBI) Heating |
| FTP/P6-20 | Tobita, K. | Concept of Power Core Components of the SlimCS Fusion DEMO Reactor |
| FTP/P6-21 | Yanagi, N. | Heat Flux Reduction by Helical Divertor Coils in the Heliotron Fusion Energy Reactor |
| FTP/P6-22 | Ariola, M. | The New JET Vertical Stabilization System with the Enhanced Radial Field Amplifier and its Relevance for ITER |
| FTP/P6-23 | Cho, S.Y. | Feasibility of Graphite Reflector in Tritium Breeding Blanket |
| FTP/P6-24 | Lee, D.W. | Progress on the Development of Fabrication Technology for the KO HCML TBM |
| FTP/P6-25 | Fischer, U. | Progress in R&D Efforts on Neutronics and Nuclear Data for Fusion Technology Applications |
| FTP/P6-26 | Hassanein, A. | Can ITER Devices Survive any Single Event of Various Plasma Instabilities? |
| FTP/P6-27 | Nakanishi, H. | Data Acquisition System for Steady State Experiments at Multi-Sites |
| FTP/P6-28 | Park, S.H. | Thermohydraulic Characteristics of KSTAR Magnet System using ITER-like Superconductors |
| FTP/P6-29 | Peyrot, M. | The JT-60SA Superconducting Magnetic System |
| FTP/P6-30 | Takechi, M. | Design Study of Plasma Control System on JT-60SA for High Beta Operation |
| FTP/P6-31 | Tatematsu, Y. | Development of Collective Thomson Scattering System using the Gyrotrons of sub-Tera Hz Region |
| FTP/P6-32 | Titus, P. | ELM and in-Vessel Coil Programs at PPPL for ITER, DIII-D, and JET |
| FTP/P6-33 | Xu, Z.Y. | Experimental Studies of MHD Flow in a Rectangular Duct with FCIs |
| FTP/P6-34 | Rubel, M.J. | Comprehensive First Mirror Test for ITER at JET with Carbon Walls |
| FTP/P6-35 | El-Aragi, G.M. | Detection of X-Ray from Micro-Focus Plasma (0.1 kJ) |
| FTP/P6-36 | Salvador, M. | Mexican Design of a Tokamak Experimental Facility |
| IFE/P6-01 | Johzaki, T. | Core Heating Scaling for Fast Ignition Experiment FIREX-I |
| IFE/P6-02 | Stephens, R.B. | Hot Electron Generation for Fast Ignition |
| IFE/P6-03 | Hegelich, B.M. | Experimental Demonstration of Key Parameters for Ion-based Fast Ignition |
| IFE/P6-04 | Murakami, M. | Progresses of Impact Ignition |
| IFE/P6-05 | Matzen, M.K.M. | Direct-Drive Concept for Z-Pinch Inertial Fusion |
| IFE/P6-06 | Logan, B.G. | Progress in U.S. Heavy Ion Fusion Research |
| IFE/P6-07 | Weaver, J.L. | Advantages of KrF Lasers for Inertial Confinement Fusion Energy |
| IFE/P6-08 | Li, C.K. | Measurements of Spontaneous Electromagnetic Fields, Plasma Flows, and Implosion Dynamics in Indirect-Drive Inertial-Confinement Fusion |
| IFE/P6-09 | Batani, D. | Proton Radiography and Fast Electron Propagation through Cylindrically Compressed Targets |
| IFE/P6-10 | Desai, T. | Control of Instabilities due to some Transient Processes in Laser Accelerated Target |
| IFE/P6-11 | Kim, Y. | Measurements of the Deuterium-Tritium Branching Ratio using ICF Implosions |
| IFE/P6-12 | Nagatomo, H. | Implosion Physics and Robust Target Design for Fast Ignition Realization Experiment |
| IFE/P6-13 | Perkins, L.J. | Investigation of the Potetial for High Gain, Shock-Ignition on the National Ignition Facility |
| IFE/P6-14 | Nakao, Y.N. | Ignition Regime and Burn Dynamics of DT-Seeded D3He Fuel for Fast Ignition Inertial Confinement Fusion |
| IFE/P6-15 | Lei, Y.A. | Low Density Volume Ignition assisted by High-Z Shell |
| IFE/P6-16 | Hora, H. | Laser-Plasma Interaction of Petawatt-Picosecond Laser Pulses with very High Contrast Ratio |
| IFE/P6-17 | Kouhi, M. | Resonance at 1H-11B Fusion applied for High Density Laser Driven Volume Ignition |
| IFE/P6-18 | Kong, H.J. | Coherent Tiled 4 Beam Combination by Phase Controlled Stimulated Brillouin Scattering Phase Conjugation Mirrors toward the Practical Laser Fusion Driver |
| IFE/P6-19 | Kalal, M. | Self-Navigation of Laser Drivers on Injected IFE Direct Drive Pellets |
| IFE/P6-20 | Ivanovsky, A.V. | Use of Super-Power Disk Explosive Magnetic Generators to Ignite a Target by Indirect Radiation of Z-Pinch X-Rays |
| IFE/P6-21 | Norimatsu, T. | Stagnation of Ablated Metal Vapor in Laser Fusion Reactor with Liquid Wall |
| IFE/P6-22 | Juárez, R. | Overview on Neutronics, Safety and Radiological Protection of HiPER Facilty |
| IFE/P6-23 | Alvarez, J. | The Role of the Spatial and Temporal Radiation Deposition in Inertial Fusion Chambers: The Case of HiPER |
| IFE/P6-24 | Cuesta-Lopez, S. | Modeling Advanced Materials for Nuclear Fusion Technology |
| IFE/P6-25 | Gonzalez-Arrabal, R. | Study of diffusion and retention of light species (H and He) in pure W and W-based materials |
| IFE/P6-26 | Hamza, A.V. | Target Fabrication for the National Ignition Facility and for Inertial Fusion Energy |
| IFE/P6-27 | Homma, H. | Recent Development of Target Fabrication and Fuel Layering Technique for FIREX project |
| IFE/P6-28 | Khaydarov, R.T. | Effect of Neutron Irradiation on the Characteristics of Laser Produced Plasma |