Current Status and Future Directions of Fusion in Japan

1
Current Status and Future Directions of Fusion in
Japan

• 15 March 2007
• Shinzaburo MATSUDA
• Executive Officer
• Japan Atomic Energy Agency

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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
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Installation of ferritic steel improved
confinement to sustain high ?NHH98(y,2) 2.2
plasmas for 23.1 s (12?R) with fBS36-45
JT-60

• 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?0lt?gta2/12 D.R. Mikkelsen, Phys. Fluids B 1
(1989) 333.
FY2007
FY2006
Maintenance period
Commissioning
Experiment
FY2007-08 experimental campaign will address
sustainment of ?N2.5-3 for gt25s
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Stabilization of RWM at small critical rotation
velocity of VC/VA0.3- A big impact on ITER
experiments and DEMO design -
RWM can be stabilized when Vgt VC critical
velocity VC was measured using Co/Counter
NBI Both DIII-D and JT-60U found VC was fairly
small VC15 km/s. Good collaboration between JAEA
and GA under Doublet III Agreement
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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.
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Ion temperature has exceeded 5 keV in moderate
density regime
Ti profile measurement by CXRS
High ion-temperature regime has been extended
towards higher density regime
Ti(0)5.20.6keV (H-main plasma)
ne1.21019m-3
Toroidal rotation profile
Large toroidal rotation and its shear observed in
association with high Ti
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Project in Kyushu University
? 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 ltlt t. (3) Systematic understanding of
the toroidal plasmas
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• AEC, Oct.2005, General Policy Report on Atomic
  Energy
• Fusion requires RD 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 RD
• Tokamak as project based RD (ITER and DEMO
  related activities including IFMIF)
• Helical, Laser Systems as science based
  researches
• Cabinet Decision, March 2006, The 3rd Phase
  (20062010) Basic Programs on Science and
  Technology
• Fusion Energy Technology as Important
  RD 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

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Road Map to Tokamak DEMO Reactors
(Oct.2005, AEC)
Structural Material Dev.
Blanket Technology
Heavy Irradiation
IFMIF
Structure Development
Fusion Engineering Research
Test Blanket Module
Component Technology
Tokamak DEMO Reactor
Fusion Plasma Research
ITERDEMO Physics Support Activities
JT-60
JT-60 Superconducting Coils
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BA Activities toward DEMO
International Fusion Energy Research Center
BA total 770M for 10 ys
30.7
DEMO Design and RD Co-ordination Center
ITER Cadarache
ITER
ITER Remote Experimentation Center
Check of experimental conditions, Machine
Control, etc
Setting Experimental Parameters
Data Acquisition and Analysis
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47.3
Satellite Tokamak
IFMIF-EVEDA
Fusion Computer Simulation Center
IFMIF
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Provisional Schedulefor Implementation of the BA
Projects
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JT-60SA (JT-60 Super Advanced) Program A combined
program of BA Program (JA-EU), and Japanese
National Program
New advanced SC tokamaks
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Summary

• The Japanese Fusion Program is directed by the
  AEC and MEXT in line with their policy reports.
• Currently,
• Tokamak Program as RD 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.

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Toward Future , Domestically, closer
collaboration between Institutes and Universities
to increase and continuously generate human
resources is Japans 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 ? 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.
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Large Helical Device (LHD)
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
Pellet Injector
Plasma vacuum vessel
ECR 84 168 GHz
World largest superconducting coil system
Magnetic energy 1 GJ
Cryogenic mass (-269 degree C) 850 t
Tolerance lt 2mm
Local Island Divertor (LID)
ICRF 25-100 MHz
NBI
NBI
8/41
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Management Structure for Broader Approach
BA Agreement
(Agreement between Japanese Government and
EURATOM)
Implementing Agency
Implementing Agency
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
EU Domestic Agency
JAEA
Audit
Project Committee
Project Committee
Project Committee
Project Leader
Project Leader
Project Leader
Satellite Tokamak(JT-60SA) Project Team
International Fusion Energy Research Center
(IFERC) Project Team
IFMIF Engineering Validation and Engineering
Design Activity (IFMIF-EVEDA) Project Team
BA Project
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Relative Allocation of Contributions from the
Parties
(in percentages)
The overall EU contribution is 339 MiEuro value
May 2005, and The overall JA contribution is 46
Byen value May 2005. Mostly in kind.
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Major Facilities and Activities in IFMIF / EVEDA
Project
Accelerator Facility
Test Facilities
Target Facility
CONCEPTUAL VIEW
Li Flow
D Beams
Irradiation Specimens of Fusion Materials
Heat Exchanger
Li Purification
Electro- Magnetic Pump
Design Integration

• Prototype Accelerator- Full power Beam Test (low
  energy part from ion source up to the first
  section of drift tube linac)
• Accelerator Test Building

• Li Loop Fabrication/Test
• Diagnostics, Erosion/corrosion, Purification
• Remote Handling Technique
• System Engineering Design

ACTIVITIES

• High Flux Test Module
• Fission Neutron Irradiation Test
• Small Specimen Test Technique
• System Engineering Design

Project Team

• Design of Buildings and Utilities

• Safety and Integration Issues

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Modification of JT-60U (JT-60SA) for BAand
National Programs

• Enhanced flexibility in aspect ratio (A2.6-3.1)
  and plasma shape.
• High power heating/current-drive system, 41MW
  for 100 s, will be prepared.
• High beta steady-state operation (?N4, fBS70)
  for DEMO and high density ELMy H-mode operation
  (ne9x1019m-3) for ITER are planned.

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JT-60 remote experiment was demonstrated from
Kyoto university
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.