Overview of Fusion Engineering in Japan

Based on long-term research activities on fusion engineering, eleven key technologies for future fusion reactors, especially for demo reactor, were selected in the Working Group of fusion research under the Council for Science and Technology, MEXT. In this paper, the recent achievement on the following key technologies will be summarized, which are strongly related to the Working Group proposal, 1) Fusion engineering research project in National Institute for Fusion Science, 2) High Tc superconducting magnets, 3) LiPb blanket system 4) Tungsten divertor and 5) Fusion engineering activities under the Broader Approach (BA) framework.

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

[2]  H. Hashizume,et al.  Transverse Stress Effects on Critical Current and Joint Resistance in Mechanical Lap Joint of a Stacked HTS Conductor , 2012, IEEE Transactions on Applied Superconductivity.

[3]  Satoshi Konishi,et al.  Neutronics of SiC-LiPb High Temperature Blanket for Tritium Production , 2013 .

[4]  H. Hashizume,et al.  Structure Improvement and Joint Resistance Estimation in Demountable Butt and Edge Joints of a Stacked REBCO Conductor Within a Metal Jacket , 2013, IEEE Transactions on Applied Superconductivity.

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

[6]  Jochen Linke,et al.  Research status and issues of tungsten plasma facing materials for ITER and beyond , 2014 .

[7]  Yusuke Kikuchi,et al.  Surface cracking and melting of different tungsten grades under transient heat and particle loads in a magnetized coaxial plasma gun , 2013 .

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

[9]  Naoyuki Hashimoto,et al.  Irradiation Effect on Tensile Property of F82H IEA and Its Joint in TITAN Project , 2013 .

[10]  Shinzaburo Matsuda,et al.  The EU/JA broader approach activities , 2007 .

[11]  Yusuke Kikuchi,et al.  Effect of Surface Damage on Thermal Response of Tungsten Monoblocks , 2015 .

[12]  Takayoshi Norimatsu,et al.  Integrated Material System Modeling of Fusion Blanket , 2013 .

[13]  Satoshi Konishi,et al.  Underwater explosive welding of tungsten to reduced-activation ferritic steel F82H , 2014 .

[14]  Satoshi Ito,et al.  Study on mechanical jointing of high temperature superconductors , 2002 .

[15]  Yuto Takeuchi,et al.  High Temperature Operation of LiPb Loop , 2011 .

[16]  Satoshi Ito,et al.  Design prospect of remountable high-temperature superconducting magnet , 2014 .

[17]  Ito Satoshi,et al.  Advanced Fusion Reactor Design using Remountable HT" SC Magnet , 2002 .

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

[19]  Satoshi Ito,et al.  Performance analysis of butt jointing in remountable HT_C superconducting magnet , 2004 .

[20]  Kenji Okuno,et al.  Behaviors of deuterium retention and microstructure change of tungsten simultaneously implanted with carbon and/or helium ions , 2013 .

[21]  Toshihiko Yamanishi,et al.  Blanket material and technology developments toward DEMO under the Broader Approach framework , 2014 .

[22]  A. Sagara,et al.  Analysis of radiation environment at divertor in helical reactor FFHR-d1 , 2014 .

[23]  H. Hashizume,et al.  Optimization of a Mechanical Bridge Joint Structure in a Stacked HTS Conductor , 2013, IEEE Transactions on Applied Superconductivity.

[24]  Takayuki Terai,et al.  Clarification of Tritium Behavior in Pb–Li Blanket System , 2013 .

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

[26]  Satoshi Ito,et al.  Overview of fundamental study on remountable HTS magnet , 2006 .

[27]  Kenji Tobita,et al.  Research and development status on fusion DEMO reactor design under the Broader Approach , 2014 .

[28]  Satoshi Konishi,et al.  Enhanced Mass Transfer of Deuterium Extracted from Falling Liquid Pb-17Li Droplets , 2013 .

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

[30]  Satoshi Konishi,et al.  Design studies of innovatively small fusion reactor based on biomass-fusion hybrid concept: GNOME , 2011 .

[31]  A. Sagara,et al.  Potential of Copper Alloys using a Divertor Heat Sink in the Helical Reactor FFHR-d1 and their Brazing Properties with Tungsten Armor by using the Typical Candidate Filler Materials , 2015 .

[32]  Takashi Shimozuma,et al.  Goal and Achievements of Large Helical Device Project , 2010 .

[33]  Satoshi Ito,et al.  Performance of a Mechanical Bridge Joint for 30-kA-Class High-Temperature Superconducting Conductors , 2014, IEEE Transactions on Applied Superconductivity.