Current Status and Future Directions of Fusion in Japan: Current Status and Future Directions of Fusion in Japan 15 Ｍarch 2007 Shinzaburo MATSUDA Executive Officer Japan Atomic Energy Agency


Government Policy Report on FusionAEC, 1992: “The 3rd Phase Basic Program on  Fusion Research and Development” 　　 * Experimental Reactor to achieve self-ignition  　　 and long pulse burn 　　 * Advanced core plasma research, and basic reactor technologies for DEMO. * Other activities (Safety, Helical, Laser, Mirror, )AEC, May 2001, “On the Promotion of the ITER Program”  MEXT,Jan. 2003, “Future Directions of Japanese Fusion  Research” * Integrate efforts into four identified major programs, while accepting challenging innovative ideas. * JT-60 SU, IFMIF, Laser, LHD: Government Policy Report on Fusion AEC, 1992: “The 3rd Phase Basic Program on Fusion Research and Development” 　　 * Experimental Reactor to achieve self-ignition 　　 and long pulse burn 　　 * Advanced core plasma research, and basic reactor technologies for DEMO. * Other activities (Safety, Helical, Laser, Mirror, ) AEC, May 2001, “On the Promotion of the ITER Program” MEXT,Jan. 2003, “Future Directions of Japanese Fusion Research” * Integrate efforts into four identified major programs, while accepting challenging innovative ideas. * JT-60 SU, IFMIF, Laser, LHD


Installation of ferritic steel improved confinement to sustain high NHH98(y,2) =2.2 plasmas for 23.1 s (~12R) with fBS=36-45%: Installation of ferritic steel improved confinement to sustain high NHH98(y,2) =2.2 plasmas for 23.1 s (~12R) with fBS=36-45% Increase in net heating power due to the FSTs installation allows flexible combination of NB units.  peaked heating profile and co-injection. 0 5 10 15 20 25 30 35 Time (s) R=0a2/12 : D.R. Mikkelsen, Phys. Fluids B 1 (1989) 333. FY2006 FY2007 Commissioning Experiment Maintenance period JT-60


Slide4: Stabilization of RWM at small critical rotation velocity of VC/VA~0.3% - A big impact on ITER experiments and DEMO design - RWM can be stabilized when V> VC : critical velocity VC was measured using Co/Counter NBI Both DIII-D and JT-60U found VC was fairly small VC~15 km/s. Good collaboration between JAEA and GA under Doublet III Agreement


NIFS carries out collaborations with 160 universities and institutions: NIFS carries out collaborations with 160 universities and institutions NIFS : Inter-University Research Institute Cooperation LHD : Facility for Inter-University Cooperation NIFS and universities share the important tasks Bilateral collaboration with four major research centers; Kyushu Univ., Osaka Univ., Kyoto Univ. and Tsukuba Univ.


Slide6: Ion temperature has exceeded 5 keV　in moderate density regime Ti profile measurement by CXRS Ti(0)=5.2±0.6keV (H-main plasma) ne=1.2×1019m-3 Toroidal rotation profile Large toroidal rotation and its shear observed in association with high Ti High ion-temperature regime has been extended towards higher density regime


Slide7: ◆ New Project ”QUEST” : Construct. 2005 – 07 FY --- Study on steady state operation of a spherical tokamak --- (1) Long duration and steady state operation of a low aspect-ratio tokamak EBW, NBI, LHCD (low density), etc. (2) PWI （Plasma-Wall Interaction) in steady state spherical tokamak plasmas 　 “Steady state” = L/R-time << t. (3) Systematic understanding of the toroidal plasmas Project in Kyushu University


Slide9: AEC, Oct.2005, “General Policy Report on Atomic Energy”: * Fusion requires R&D efforts from a long range perspective and is regarded to be in a stage of exploring its feasibility/validity as engineering system. AEC, Oct. 2005 , “On the Promotion of Future Fusion R&D” Tokamak as project based R&D (ITER and DEMO related activities including IFMIF) Helical, Laser Systems as science based researches Cabinet Decision, March 2006, “The 3rd Phase (2006~2010) Basic Programs on Science and Technology” “Fusion Energy Technology” as “Important R&D Item”, and “ITER Project” as “Strategic Important Technology” MEXT, April 2007 “Promotion of the Japanese Fusion Research led by ITER and Broader Approach” * Review of the Big Projects * Strong need for next generation researchers * Reform of “Fusion Forum” to provide opportunities for xx


Slide10: JT-60 Fusion Plasma Research Tokamak DEMO Reactor ITER&DEMO Physics Support Activities Component Technology Test Blanket Module Blanket Technology Heavy Irradiation IFMIF Structure Development Structural Material Dev. Fusion Engineering Research JT-60 Superconducting Coils Road Map to Tokamak DEMO Reactors (Oct.2005, AEC)


Slide11: ITER　Cadarache Satellite Tokamak International Fusion Energy Research Center DEMO Design and R&D Co-ordination Center ITER Remote Experimentation Center ITER Data Acquisition and Analysis Setting Experimental Parameters IFMIF-EVEDA IFMIF Fusion Computer Simulation Center Check of experimental conditions, Machine Control, etc BA Activities toward DEMO BA total ~770M$ for 10 ys 30.7% 22% 47.3%


Slide12: Provisional Schedule for Implementation of the BA Projects


Slide13: JT-60SA (JT-60 Super Advanced) Program A combined program of BA Program (JA-EU), and Japanese National Program


Summary: Summary The Japanese Fusion Program is directed by the AEC and MEXT in line with their policy reports. Currently, Tokamak Program as R&D Project is carried out mostly in the framework of ITER and BA Activities, and partly in the National Program. Ratification process of the ITER and BA Agreements have been completed on 9th May by the Diets. The JAEA will be nominated as Domestic Agency for ITER and Implementing Agency for BA. Helical and Laser Approaches as science program are generating world pioneering data.


Toward Future , Domestically, closer collaboration between Institutes and Universities to increase and continuously generate human resources is Japan’s major issue from long range perspective. Also in world-wide, there is strong need for next generation researchers for fusion programs. To this end, frontier facilities (such as Doublet ⅲ　and JT-60SA) may provide good opportunities if one uses the framework of international agreement such as experienced in the JAERI-DOE fusion collaboration. The BA Activities are open to other ITER Parties and US participation will be quite welcome.: Toward Future , Domestically, closer collaboration between Institutes and Universities to increase and continuously generate human resources is Japan’s major issue from long range perspective. Also in world-wide, there is strong need for next generation researchers for fusion programs. To this end, frontier facilities (such as Doublet ⅲ　and JT-60SA) may provide good opportunities if one uses the framework of international agreement such as experienced in the JAERI-DOE fusion collaboration. The BA Activities are open to other ITER Parties and US participation will be quite welcome.


Slide17: External diameter 13.5 m Plasma major radius 3.9 m Plasma minor radius 0.6 m Plasma volume 30 m3 Magnetic field 3 T Total weight 1,500 t NBI NBI Local Island Divertor (LID) ECR 84 – 168 GHz ICRF 25-100 MHz Plasma vacuum vessel World largest superconducting coil system Magnetic energy 1 GJ Cryogenic mass (-269 degree C) 850 t Tolerance < 2mm Large Helical Device (LHD) Pellet Injector 8/41


Slide19: Steering Committee Appointment of a Project Leader Approval of Project Plans, Work Programmes and Annual Reports Approval of the Structure of the Project Teams Other Functions to Direct and Supervise JAEA BA Project EU Domestic Agency BA Agreement (Agreement between Japanese Government and EURATOM) Implementing Agency Project Leader IFMIF Engineering Validation and Engineering Design Activity （IFMIF-EVEDA） Project Team Project Committee Project Leader International Fusion Energy Research Center （IFERC） Project Team Project Committee Project Leader Satellite Tokamak （JT-60SA） Project Team Audit Project Committee Implementing Agency Management Structure for Broader Approach


Slide20: The overall EU contribution is 339 MiEuro value May 2005, and The overall JA contribution is 46 Byen value May 2005. Mostly in kind. Relative Allocation of Contributions from the Parties (in percentages)


Slide21: Li Loop Fabrication/Test Diagnostics, Erosion/corrosion, Purification Remote Handling Technique System Engineering Design Prototype Accelerator- Full power Beam Test (low energy part from ion source up to the first section of drift tube linac) Accelerator Test Building High Flux Test Module Fission Neutron Irradiation Test Small Specimen Test Technique System Engineering Design　　 　Design of Buildings and Utilities 　　 CONCEPTUAL VIEW Accelerator Facility Test Facilities Target Facility Design Integration Project Team Irradiation Specimens of Fusion Materials Electro- Magnetic Pump Li Flow Heat Exchanger D+ Beams Li Purification 　Safety and Integration Issues 　　 ACTIVITIES Major Facilities and Activities in IFMIF / EVEDA Project


Slide22: Enhanced flexibility in aspect ratio (A=2.6-3.1) and plasma shape. High power heating/current-drive system, 41MW for 100 s, will be prepared. High beta steady-state operation (N~4, fBS~70%) for DEMO and high density ELMy H-mode operation (ne~9x1019m-3) for ITER are planned. Modification of JT-60U (JT-60SA) for BA and National Programs


Slide23: • High sequrity remote experimental system of JT-60 has been developed using ITBL technology. • A step toward remote experimental center at Rokkasho. • Remote experiments from abroad is under consideration. JT-60 remote experiment was demonstrated from Kyoto university