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Fusion Energy Development in Japan

Fusion Power Associates Annual Meeting and Symposium October 11-12 in Washington, DC. Fusion Energy Development in Japan. Director General Fusion Energy Research Directorate Naka Fusion Institute Japan Atomic Energy Agency. Masahiro SEKI. OUTLINE. Road map to Fusion Energy

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Fusion Energy Development in Japan

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  1. Fusion Power Associates Annual Meeting and Symposium October 11-12 in Washington, DC Fusion Energy Development in Japan Director General Fusion Energy Research Directorate Naka Fusion Institute Japan Atomic Energy Agency Masahiro SEKI

  2. OUTLINE Road map to Fusion Energy Broader Approach Projects Candidate Projects Investigations in JA Discussions between EU and JA, 3.Fusion Energy Research in JAEA JAEA - New Organization JAERI + JNC Recent Outcomes and Future Plan 4. Summary

  3. ITER Test Blanket Module 1. Road map to Fusion Energy Structural Material Dev. Blanket Technology Heavy Irradiation IFMIF Structure Development Fusion Engineering Research SC Magnet Tritium Handling Plasma Facing component Remote Maintenance Heating System Safety Component Technology DEMO Reactor Fusion Plasma Research Confinement Improvement Impurity Control Improvement of Stability ITER&DEMO Physics Support Activities JT-60 National Centralized Tokamak

  4. Cont DEMO Design 2. Broader Approach Projects Contribution : (50%+8%:EU)+(10%+8%:JA)+10%x4(US,RF,KO,CN) 100%(ITER)+16%(Broader Approach) ITER EU JA Simulation IFMIF-EVEDA Remote Center Satellite Tokamak 50%+8% Arrangement between EU&JA 10% 10%+8% 10% 10% 10%

  5. Candidate Projects Candidate projects, identified in the final report of the six-party broader approach workshops in January 2004, include: -IFMIF (EVEDA and/or facility) -ITER Research Center(s) including a computer simulation center for fusion science a center for remote experimentation -Fusion power plant technology coordination center, including center for international design activities for demonstration reactors -A new plasma experimental device (Satellite Tokamak)Projects which are not included in the above list could be chosen at the initiative of the non-Host provided that they contribute to early realization of fusion energy and the Host and non-Host jointly decide to undertake them.

  6. Important Points contribute to early realization of fusion energy make the best use of fusion research potential in Japan attractive projects for fusion scientists in the world balanced approach through multiple projects for synergy and long term personnel training Discussions in Japan Committee on ITER Project Promotion Chair: A. Arima (Former Minister of Education, and Science&Technology) S. Takamura(Nagoya Univ.), S. Tanaka(Tokyo Univ.), S.Matsuda(JAERI), O.Motojima(NIFS) Report of Committee Recommended Projects International Fusion Energy Research Center (ITER Remote Experimentation Center, Fusion Simulation Center, Fusion Power Plant Technology Coordination Center, IFMIF-EVEDA) Satellite Tokamak (Superconducting Modification of JT-60)

  7. EU-JA Bilateral Discussion 2005.07.21 EU-JA Technical Meeting (Garching) 2005.08.25 EU-JA IFMIF-EVEDA Meeting(Naka) 2005.08.26 EU-JA Technical Meeting (Tokyo) 2005.09.15 EU-JA Technical Meeting (Paris) 2005.09.19 Informal Meeting on Satellite Tokamak(Geneva) 2005.10.05 EU-JA Satellite Tokamak Meeting(Naka) IFMIF-EVEDA: Common Understanding reached on work plan of EVEDA Satellite Tokamak: Interim Report expected in Mid. Nov. 2005 Remote Center: Discussed a concept of Remote Experimentation Center Simulation Center&DEMO Centers: Importance recognized By the end of 2005, selection of the projects is to be finalized.

  8. International Fusion Energy Research Center ITER Facility Center International Fusion Energy Research Center Building ITER ITER Remote Experimentation Center Check of experimental conditions, Machine Control, etc Setting Experimental Parameters Data Acquisition and Analysis Computer Simulation Center for Fusion Science Satellite Tokamak Fusion Power Plant Technology Coordination Center IFMIF-EVEDA (~200 people icluding staff, supporting staff, and visiting researchers) IFMIF

  9. Computer Simulation Center for Fusion Science Computational Simulation Center for Fusion Science will provide EU and JA researchers with an excellent environment for computer simulations on burning plasmas and advanced steady-state plasmas, fusion DEMO plant design, development of advanced fusion materials, etc. by using high speed grid computers, aiming at contributing to efficient and effective execution of the ITER project and early realization of fusion energy. Processor Performance : ~100 TFLOPS ・Optimization of Operation Scenarios for ITER ・Optimization of ITER auxiliary systems which come later in the construction of ITER ・Understanding burning plasma in ITER etc. Development of advanced materials High Speed Grid Computer ・Design of Fusion DEMO Plant ・Exploring operational regimes and issues complementary to those being addressed in ITER (steady state operation with higher normalized plasma pressure, control of power fluxes to walls, etc.) MHD in Core Plasma, Plasma Disruption MHD phenomena at plasma boundary Turbulence in Peripheral Plasma Ion turbulence Tokamak Simulator Divertor Heat/Particle Flux Electron turbulence

  10. Fusion Power Plant Technology Coordination Center Conceptual design studies will be implemented jointly by EU and JA in order to provide a common concept of DEMO plant, schedule of DEMO project and it’s cost estimation, including identification of physics and engineering R&D issues necessary for early realization of fusion power plant. Preliminary R&Ds, such as advanced SC magnets, low activation structural materials, blanket for DEMO plant will also be performed. Information Exchange, Conceptual Design Studies, preliminary R&D Design of Fusion Power Plant Japan：SSTR、A-SSTR、CREST、VECTOR EU ：SEAFP、PPCS A、PPCS B、PPCS C、PPCS D Safety Desgin and Analysis Evaluation of Cost and schedule Conceptual Design of Core System Conceptual Design of DEMO Plant 1020 LWR Fusion Reactor (SSTR) 1018 Toxic hazard potentials due to inhalation intake (m3) 1016 Coal fired power 1014 1012 10-4 10-2 10o 102 104 106 Year

  11. ITER Satellite Tokamak Machine JT-60 Modification with SC Magnets Directly Suport ITER DEMO Reactor For ITER Optimize Operation Scenario Optimize ITER auxiliary systems Training scientists, engineers Understand ITER Physics issues Complement ITER outputs In preparation of DEMO For DEMO Steady State Operation Advanced Plasma Regimes (High bN regime) Control of Power Flux to Walls Satellite Tokamak JT-60 Ip=5.5MA, Bt=2.76T, Rp=2.97m, a=1.13m Superconducting Tokamak Based on Joint Report of EU/JA Expert Gr. Meeting 18-19 April 2004, Culham on BA for Fusion Power

  12. IFMIF-EVEDA IFMIF Test & verify materials performance for design, construction, licensing and safe operation of DEMO ~2015 DEMO Reactor Operation Construction ~2025 Sufficient Information for DEMO Construction EVEDA EVEDA Task Design Integration Ion Source Test Accelerator Test Diagnostics System Design Main Loop Model Diagnostics Li Purification Remote Handling System Design Test Module Small Specimen Test Diagnostics Remote Handling System Design Target Accelerator Test Cell DT Linac Injector 40 MeV RFQ 0.1 MeV Li Purification Loop 5 MeV

  13. BA Projects leading to construction of DEMO 10years 10years 10years Performance Extension Construction Basic Performance Decom. ITER Project Test of Breeding Blanket Module Remote Experimentation&Distributed Coordination BA IFMIF Construction BA IFMIF-EVEDA Operation Fusion Power Plant Tech. Coordination Center Conceptual Design Study Physics&Technology R&D BA EDA R&D Construction Operation BA Computer Simulation Center Burning Plasma Simulation Burning Physics & DEMO Plasma Simulation JA&EU ITER&DEMO Physics Support Activities Upgrade of JT-60 BA Satellite Tokamak Commissioning

  14. 6000 5023 4948 4679 4608 4493 4445 4386 4000 2000 0 3000 3104 2896 2813 2000 2630 2271 2231 1912 1000 0 1999 2000 2001 2002 2003 2004 2005 3. Fusion Energy Research in JAEA Two organizations JAERI and JNC were integrated into the new independent administrative agency “Japan Atomic Energy Agency (JAEA)” on 1st Oct. 2005. Staff(persons) Horonobe Center JNC Mutsu Estab. JAERI Takasaki Institute Budget(100M¥) Naka Institute Tono Center Tokai Center Tsuruga Headquarters JNC Headquarters Ningyou-toge Center JAERI Oarai Center Year Main Enterprises Formation of a solid basis for nuclear R&D Establishment of nuclear fuel cycle technology Promotion of fusion energy R&D Kansai Institute

  15. ( RESEARCH DIRECTORATES ) Nuclear Safety Research Center Advanced Science Research Center Nuclear Science and Technology Quantum Beam Science Fusion Energy Research Next Generation Atomic Energy System R&D Nuclear Fuel Cycle Technology Development Geological Isolation Research and Development Backend Promotion Research Organization of JAEA President Vice President Executive Directors ( RESEARCH AND DEVELOPMENT SITES ) Tsuruga Office Tokai Research and Development Center O-arai Research and Development Center Naka Fusion Institute Takasaki Radiation Chemistry Research Institute Kansai Research Institute Horonobe Underground Research Center Tono Geoscience Center Ningyo-toge Environmental Engineering Center Mutsu Establishment

  16. Fusion Research Organization in JAEA DG: M.Seki DG:M.Seki Fusion Energy Research Directorate Naka Fusion Institute Facilities Research Office of Research Promotion S. Seki H. Kobayashi Dept. of Administration ITER Project Promotion Gr Y. Okumura Broader Approach Project Promotion Gr K. Ushigusa Research Coordination Gr K. Ushigusa Division of ITER Project T. Tsunematsu JT-60/NCT Division of Advanced Plasma Research H. Ninomiya Division of Tokamak System Technology M. Kuriyama Division of Fusion Energy Technology H. Takatsu

  17. Research Plan of JT-60 in 2005 Targets Long sustainment of High Performance - n=2-2.5 and HH~1 for >25s - higher bootstrap current fraction (IBS/Ip=0.7-0.8) - high fusion triple product nT~5x1019m-3skeV for 20s - high H-factor in wall-saturated condition 2. Attainment of n >3.5 beyond the free-boundary ideal MHD limit wall stabilization, plasma rotation(BT ripple reduction with ferritic plates) 3. Expand quasi-steady fully non-inductive current drive performance Inspections, commissioning operation

  18. N=2.3 sustained for 22.3s(~13.1R) PNB(MW) Ip(MA) P-NB N-NB N Ti (keV) Te(keV) 10 20 30 0 Time (s) Long Time Sustainment of High Performance Plasmas Target

  19. June, 2005 May, 2005 Ferrite tiles Graphite tiles 5° 9° W ferritic plates W/O ferritic plates Installation of ferritic plates inside the VV, completed (forwall stabilization experiments) Reduction of ripple well by ferritic plates () 8Cr2W ferritic steel (Bsat〜1.8T) Thickness : 23mm

  20. National Centralized Tokamak Device - • Satellite Tokamak for ITER - JT-60 Modification Program SC device with a break-even class performance Sustain high beta (N=3.5-5.5) non-inductive CD Mobility and flexibility as a DD device Lower aspect ratio (A=2.6: 3.1 in ITER) High shape factor (S=7: <5 in ITER) Feedback control (internal RW coils) Profile control (off-axis NBCD for RS) Test of Plasma Facing Component for DEMO Compatibility test of RAF Test candidate divertor modules for DEMO Sample station (material plasma test)

  21. Fusion Engineering R&D in 2005 Blanket Technology Preparation for engineering-scale mockup testing of ITER TBM Evaluation of thermal-hydraulic, thermo-mechanical and neutronics performances Development of tritium recovery technology Development of mass-production technology of blanket materials Materials Development Accumulation of neutron irradiation data for F82H Using HFIR(ORNL) to the level over 50dpa Technical preparations for IFMIF-EVEDA Basic Fusion Technology Continue basic R&Ds in fusion technology areas vacuum, advanced superconducting magnet, tritium-safety, neutronics, beam and microwave technologies Expand and deepen technical basis to contribute ITER construction, ITER-TBM, IFMIF and DEMO Encourage spin-off of fusion technologies to other areas (industry and scientific research)

  22. Results of trial fabrication (Internal Tin) Hysteresis Loss for 3T (mJ/cm3) (Bronze) Spec. for Bronze process Spec. for Internal Tin Critical Current Density @12T, 4.2K, 0.1mV/cm (A/mm2) 1.Preparation for ITER TF coil case procurement 2.Trial fabrication of ITER Nb3Sn strands Superconducting Magnet Development • The following full-scale forging materials for a TF coil case have been produced. The qualification tests of these materials are under way. • - JJ1: 3.7m L x 0.94m W x 0.39m t • (used in the red parts of the figure) • -Strengthened 316LN: 4.7m L x 0.96m W x 0.43m t • (used in the blue parts of the figure) • Strengthened 316LN (ST316LN) has higher nitrogen content (N0.17%) than the ordinary 316LN. It has been demonstrated that ST316LN can satisfy the ITER requirement (yield strength of more than 850MPa at 4K) up to the thickness of 430mm. • Trial fabrication of Nb3Sn strands has been performed. • (about 0.1 ton / manufacturer x four manufacturers) • Both bronze process and internal tin process have satisfied the ITER requirements. JJ1 Forging 3.Development of High Temp. Superconductor Silver (white) HTS (gray) • Reduction of silver content in a HTS wire is desired in order to decrease irradiated wastes in a fusion power plant. • By optimizing the configuration of HTS filaments and silver sheath, 23% reduction in silver has been achieved and its critical current was increased by 20%. Ic~100A at 17.5T Silver content was reduced by 23%. Ic~120A at 17.5T

  23. 2.0 1.5 1.0 0.5 0 Power (MW) 出力 0 20 40 60 80 Beam Current (A) Neutral Beam (NB) system Electron Cyclotron system Heating and Current Drive System Gyrotron of 1.5MW/CW relevant oscillation mode (TE31,12 mode) 170GHz 1msec 1.6MW • Stable operation of 1.6MW at 170GHz • Beam acceleration in progress, • - 836 keV, 146 A/m2 (0.2 A) H-. • Power density is twice higher • than existing systems. • H- ion beams of ITER relevant powerdensity obtained at MeV level energy Long Pulse 170GHzGyrotron for ITER • 0.5MW/100sec, 0.9MW/9sec • 0.2MW/500sec (in progress)

  24. Calculation Experiment 1st layer Overall C/E=1.04 C/E=1.01 2nd layer C/E=1.08 50 µm 50 µm 1. Fabrication Technology Develop. for TBM Box - New Hot Isostatic Press(HIP) conditions for a TBM box made of Reduced Activation Ferritic Steel (RAFS) have been developed to keep fine grain sizes which ensure higher fracture toughness. 2.Neutronics Experiments for TBM. - Prediction uncertainty of the tritium production rate has been evaluated to be less than 8% by using a simulated TBM mockup, which consists of 2 tritium breeder (Li2TiO3) layers and 3 RAFS layers. ITER Test Blanket Module (TBM) Development RAFS TBM box made by HIP Experimental Tritium Production Rate compared with Calculation Cooling Channels Experiments have been carried out with 14 MeV neutrons in the JAERI FNS facility. First Wall Previous HIP Condition New HIP Condition HIP Temp.: 1040°C HIP Temp.: 1100°C followed by normalizing at 950°C Coarsening of grain size occurred after HIP. Fine grain size has been achieved after HIP. Ratio of calculation results to experimental values (C/Es) have been clarified to be less than 8%.

  25. 1000 HFIR Irradiation Exp Design Window for Reduced Activation Ferritic/Martensitic Steel (RAFMS) Target RB Rabbit RAFMS Database Temperature (°C) 500 Power Plant ~2025 or later (IFMIF) ~2010 PRESENT ITER SS316 0 100 50 150 200 0 Neutron Irradiation Damage (dpa), 1MWa/m2~10dpa Tensile Property of F82H Fatigue after irradiation (F82H) 2004 ~ 2009 F82H RAFMS as candidate materials for blanket first wall Fusion Materials Development • Database up to 20~30 dpa obtained by HFIR irradiation exhibits promising results • Advanced heat treatment successfully reduced the excess hardness after irradiation • Irradiation effect on fatigue is revealed to be small (<450C) • IFMIF will be used to obtain database in >50dpa region (Low cycle fatigue) The small radiation effect ensures that current design method is applicable for fatigue of TBM Advanced heat treatment to reduce irradiation effects is revealed to be successful

  26. Summary Japanese Fusion Energy Research will concentrate on - ITER Project as an associate host party - Broader Approach Projects to support ITER and to contribute to early realization of fusion energy Selection of the Broader Approach Projects is in progress in Japan. Intense discussions are also being made between EU and Japan. JAEA will be designated to take care of ITER and Broader Approach Projects. Steady progress has been achieved in 2004-2005 period in both plasma research and fusion technology in JAERI.

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