Presentation Title
|
|
Agenda (ver. 4)
|
|
Overview of Design and R&D for the Helical Fusion Reactor FFHR-d1
| A. Sagara (NIFS) |
Overview of DEMO Design Activity by the Joint Special Design Team
| K. Tobita (QST) |
Overview of the Fusion Nuclear Science Facility, and New Liquid Metal PFCs Study
| C.E. Kessel, PPPL & the FESS Team |
Discussion on DEMO Operation Plan in Japan
| R. Hiwatari (QST) |
Design Window and Cost Analysis of the Helical Fusion Reactor
| T. Goto (NIFS) |
| FNSF Systems Studies | C.E. Kessel, PPPL & the FESS Team |
Recent Physics Design on Japanese DEMO
| Y. Sakamoto (QST) |
Ion Heating through Equipartition Process and the First Results of High-Ti Experiments with Deuterium in LHD
| H. Takahashi (NIFS) |
Recent Status of Power Exhaust Study and Divertor Design for Japan DEMO
| N. Asakura (QST) |
Physics Strategy, Core Plasma Physics and SOL/Divertor Physics
| C.E Kessel, PPPL & the FESS Team |
Study on Ion Temperature Anisotropy in SOL Plasmas with a Virtual Divertor Model
| Y. Ogawa (Univ of Tokyo), S. Togo (Univ of Tsukuba) and T. Takizuka |
Energy Dissipation by Vapor Shielding during Transient Loads
| K. Ibano (Osaka Univ) |
A Review of Recent Studies on Particle Recycling from Liquid Metals under Steady State Plasma Bombardment
| Y. Hirooka, H. Bi (NIFS) |
Hydrogen Isotopes Transport in Liquid Metals under Steady State Plasma Bombardment
| H. Bi, Y. Hirooka (NIFS) |
REVOLVER-D: The Ergodic Limiter/Divertor of Molten Tin Shower Jets for FFHR-d1 and c1
| J. Miyazawa (NIFS) & the FFHR Design Group |
A Conceptual Design for a Liquid Metal Divertor
| R. Majeski, T. Brown, M. Hvasta, E. Kolemen, J. Menard (PPPL) |
Electrode-free Actively Convected Liquid Metal Divertor
| M. Shimada (QST) |
Liquid Metal PFC Thermo-mechanics
| A. Khodak (PPPL) |
Advanced First Wall Concepts for High Heat Flux in the FNSF
| M.S. Tillack (QED), Y. Huang, N.M. Ghoniem (UCLA) |
Benefits and Challenges of Liquid Metal Plasma Facing Components
| R. Majeski (PPPL) |
Heat Flux Mitigation and Maintenance Issues of the Helical-Divertor for the Helical Fusion Reactor FFHR
| N. Yanagi (NIFS) |
New Model Development in FW Heat Load Analysis
| Y. Miyoshi (QST) |
Investigation on the Magnetic Field Distortion by Ferromagnetism of the Blanket for the Helical Fusion Reactor
| X. Ji (NIFS/ASIPP), N. Yanagi, T. Goto, Hitoshi Tamura, J. Miyazawa, A. Sagara (NIFS); S. Wang, M. Qi, Y. Song (ASIPP) |
Blanket Analysis for the FNSF: LiPb Breeder, Thermo-Mechanics, Thermal Hydraulics, and Tritium
| M. Tillack (QED); Y. Huang, N. Ghoniem, S. Smolentsev (UCLA); P. Humrickhouse (INL); E. Marriott, A. Davis (UWM) |
Estimation of MHD Heat Transfer Degradation for Thermal Design Utilizing Molten Salt Coolants
| Y. Yamamoto (Univ of Yamanashi), T. Kunugi (Kyoto Univ) |
Planned and Unplanned Transients in PFCs
| J. Blanchard (UWM) |
FNSF Magnets: TF Winding Pack - Wire & CICC Design
| Y. Zhai (PPPL) |
Design of Support Structure for the Magnet System of FFHR-d1
| H. Tamura (NIFS) |
Conceptual Design for Remote Maintenance on Japanese DEMO
| H. Utoh (QST) |
Detailed Thermo-mechanics and Accident Modeling for Blanket Modules
| A. Khodak, X. Cheng (PPPL) |
Neutronics Analysis on the Blanket of the Helical Fusion Reactor FFHR-d1
| T. Tanaka (NIFS) |
Neutronics Approaches for DEMO Conceptual Design
| Y. Someya (QST) |
