Progress in the Conceptual Design of the Helical Fusion Reactor FFHR-d1

[1]  N. Yanagi,et al.  Advanced high-temperature superconducting magnet for fusion reactors: Segment fabrication and joint technique , 2018, Fusion Engineering and Design.

[2]  Masahiro Tanaka,et al.  Preparation and Commissioning for the LHD Deuterium Experiment , 2018, IEEE Transactions on Plasma Science.

[3]  Y. Takeiri Prospect Toward Steady-State Helical Fusion Reactor Based on Progress of LHD Project Entering the Deuterium Experiment Phase , 2018, IEEE Transactions on Plasma Science.

[4]  A. Sagara,et al.  Conceptual design of a liquid metal limiter/divertor system for the FFHR-d1 , 2017 .

[5]  A. Sagara,et al.  Design modification of structural components for the helical fusion reactor FFHR-d1 with challenging options , 2017 .

[6]  N. Yanagi,et al.  Two conceptual designs of helical fusion reactor FFHR-d1A based on ITER technologies and challenging ideas , 2017 .

[7]  A. Sagara,et al.  Cartridge-Type Helical Blankets Aiming at Easy Construction and Maintenance for the FFHR-d1 , 2017 .

[8]  A. Sagara,et al.  Development of a real-time simulation tool towards self-consistent scenario of plasma start-up and sustainment on helical fusion reactor FFHR-d1 , 2017 .

[9]  A. Sagara,et al.  Magnet design with 100-kA HTS STARS conductors for the helical fusion reactor , 2016 .

[10]  A. Sagara,et al.  Proposal for the Method of Maintaining Breeder Blankets in the LHD-Type Helical Fusion Reactor FFHR , 2016 .

[11]  A. Sagara,et al.  NITA Coil—Innovation for Enlarging the Blanket Space in the Helical Fusion Reactor , 2016 .

[12]  A. Sagara,et al.  Multiscale Stress Analysis and 3D Fitting Structure of Superconducting Coils for the Helical Fusion Reactor , 2016, IEEE Transactions on Applied Superconductivity.

[13]  N. Yusa,et al.  Reducing Joint Resistance by Heat Treatment During Fabrication of a Mechanical Joint of High-Temperature Superconducting Conductors , 2016, IEEE Transactions on Applied Superconductivity.

[14]  A. Sagara,et al.  Mechanical and Electrical Characteristics of a Bridge-Type Mechanical Lap Joint of HTS STARS Conductors , 2016, IEEE Transactions on Applied Superconductivity.

[15]  R. Wolf,et al.  From W7-X to a HELIAS fusion power plant: motivation and options for an intermediate-step burning-plasma stellarator , 2016 .

[16]  A. Sagara,et al.  Novel divertor design to mitigate neutron irradiation in the helical reactor FFHR-d1 , 2015 .

[17]  A. Sagara,et al.  Hydrogen solubility in FLiNaK mixed with titanium powder , 2015 .

[18]  W. Shmayda,et al.  Dependence of Tritium Release from Stainless Steel on Temperature and Water Vapor , 2015 .

[19]  A. Sagara,et al.  First Operation of the Flinak/LiPb Twin Loop Orosh2i-2 with a 3T SC Magnet for R&D of Liquid Blanket for Fusion Reactor , 2015 .

[20]  N. Yanagi,et al.  Fundamental Investigation on Tensile Characteristics of a Mechanical Lap Joint of REBCO Tapes , 2015, IEEE Transactions on Applied Superconductivity.

[21]  A. Sagara,et al.  Measurement and Analysis of Critical Current of 100-kA Class Simply-Stacked HTS Conductors , 2015, IEEE Transactions on Applied Superconductivity.

[22]  Satoshi Ito,et al.  Design and development of high-temperature superconducting magnet system with joint-winding for the helical fusion reactor , 2015 .

[23]  Francisco L. Tabarés,et al.  Present status of liquid metal research for a fusion reactor , 2015 .

[24]  A. Sagara,et al.  Helical reactor design FFHR-d1 and c1 for steady-state DEMO , 2014 .

[25]  Takuya Goto,et al.  Design of structural components for the helical reactor FFHR-d1A , 2014 .

[26]  Satoshi Ito,et al.  Bridge-Type Mechanical Lap Joint of a 100 kA-Class HTS Conductor having Stacks of GdBCO Tapes ∗) , 2014 .

[27]  M. Shoji,et al.  First EMC3‐EIRENE Simulations with Divertor Legs of LHD in Realistic Device Geometry , 2014 .

[28]  A. Sagara,et al.  Critical Current Measurement of 30 kA-Class HTS Conductor Samples , 2014, IEEE Transactions on Applied Superconductivity.

[29]  Masataka Iwakuma,et al.  Feasibility of HTS Magnet Option for Fusion Reactors , 2014 .

[30]  A. Sagara,et al.  Radial-build design and support system for the helical DEMO reactor FFHR-d1 , 2013 .

[31]  S. Murakami,et al.  Study of α-particle confinement in an LHD-type heliotron reactor , 2013 .

[32]  S. Okamura Configuration Optimization of a Planar-Axis Stellarator with a Reduced Shafranov Shift , 2013 .

[33]  S. Okamura Configuration optimization of planar-axis stellarator with minimum number of Fourier modes of boundary shape , 2013 .

[34]  M. Kobayashi,et al.  Control of 3D edge radiation structure with resonant magnetic perturbation fields applied to the stochastic layer and stabilization of radiative divertor plasma in LHD , 2013 .

[35]  A. Sagara,et al.  Neutronics Investigations for Helical DEMO Reactor FFHR-d1 , 2012 .

[36]  H. Ichikawa,et al.  Underwater Laser Beam Welding for Nuclear Reactors , 2012 .

[37]  A. Sagara,et al.  Design Window Analysis for the Helical DEMO Reactor FFHR-d1 , 2012 .

[38]  R. Gallix,et al.  Validation of welding technology for ITER TF coil structures , 2011 .

[39]  A. Sagara,et al.  Direct extrapolation of radial profile data to a self-ignited fusion reactor based on the gyro-Bohm model , 2011 .

[40]  Nagato Yanagi,et al.  Design Progress on the High-Temperature Superconducting Coil Option for the Heliotron-Type Fusion Energy Reactor FFHR , 2011 .

[41]  D. Park,et al.  HTS Pancake Coils Without Turn-to-Turn Insulation , 2011, IEEE Transactions on Applied Superconductivity.

[42]  S. Imagawa,et al.  Heat flux reduction by helical divertor coils in the heliotron fusion energy reactor , 2011 .

[43]  Farrokh Najmabadi,et al.  Review of stellarator/heliotron design issues towards MFE DEMO , 2010 .

[44]  M. Itagaki,et al.  Monte Carlo Study Based on a Real Coordinate System for Tangentially Injected High-Energy Particles in the Large Helical Device , 2010 .

[45]  H. Yamada,et al.  Edge Plasma Transport in the Helical Divertor Configuration in LHD , 2010 .

[46]  Laila A. El-Guebaly,et al.  Fifty Years of Magnetic Fusion Research (1958–2008): Brief Historical Overview and Discussion of Future Trends , 2010 .

[47]  Osamu Motojima,et al.  Optimization activities on design studies of LHD-type reactor FFHR , 2008 .

[48]  Minami Yoda,et al.  The ARIES-CS Compact Stellarator Fusion Power Plant , 2008 .

[49]  Nagato Yanagi,et al.  Concept of magnet systems for LHD-type reactor , 2008 .

[50]  A. Sagara,et al.  High-Temperature Superconducting Coil Option for the LHD-Type Fusion Energy Reactor FFHR , 2008 .

[51]  H. Yamada,et al.  Development of net-current free heliotron plasmas in the Large Helical Device , 2008 .

[52]  Naoki Mizuguchi,et al.  Conceptual design activities and key issues on LHD-type reactor FFHR , 2006 .

[53]  Osamu Motojima,et al.  Impact of real-time magnetic axis sweeping on steady state divertor operation in LHD , 2006 .

[54]  K. Kawahata,et al.  Review of Divertor Studies in LHD , 2006 .

[55]  M. Okamoto,et al.  Formation and healing of n = 1 magnetic islands in LHD equilibrium , 2005 .

[56]  Satoshi Ito,et al.  Proposal of mechanically jointed superconducting magnet using high critical temperature superconductors , 2002 .

[57]  Masaki Osakabe,et al.  The divertor plasma characteristics in the Large Helical Device , 2002 .

[58]  C. D. Beidler,et al.  Stellarator Fusion Reactors - an Overview , 2002 .

[59]  Akira Kohyama,et al.  Design studies of helical-type fusion reactor FFHR , 1998 .

[60]  A. Boozer What is a stellarator , 1998 .

[61]  Osamu Motojima,et al.  Blanket and divertor design for force free helical reactor (FFHR) , 1995 .

[62]  A. Sagara,et al.  The large helical device (LHD) helical divertor , 1994 .

[63]  O. Motojima,et al.  Contact resistance of demountable multi-pin joint for superconducting helical coil , 1987 .

[64]  H. Nakashima,et al.  Neutron Streaming Analysis for Helical Geometry System, Heliotron-H Fusion Power Reactor , 1986 .

[65]  Y. Seki,et al.  Design Study of Swimming Pool Type Tokamak Reactor (SPTR) , 1982 .

[66]  C. Gourdon,et al.  The torsatron without toroidal field coils as a solution of the divertor problem , 1971 .

[67]  K. Uo The Confinement of Plasma by the Heliotron Magnetic Field , 1961 .