Fusion Energy Development in Japan

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

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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
ITERDEMO Physics Support Activities
JT-60
National Centralized Tokamak
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2. Broader Approach Projects
Cont
Contribution (50 8EU)(108JA)10x4(US,
RF,KO,CN)
100(ITER) 16(Broader Approach)
ITER
EU
JA
Simulation
IFMIF-EVEDA
Remote Center
Satellite Tokamak
508
Arrangement between EUJA
10
108
10
10
10
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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.
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Discussions in Japan
Committee on ITER Project Promotion
Chair A. Arima (Former Minister of Education,
and ScienceTechnology) 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)
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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 CenterDEMO Centers
Importance recognized
By the end of 2005, selection of the projects is
to be finalized.
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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
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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 phenomena at plasma boundary
MHD in Core Plasma, Plasma Disruption
Turbulence in Peripheral Plasma
Ion turbulence
Tokamak Simulator
Divertor Heat/Particle Flux
Electron turbulence
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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 its cost estimation, including
identification of physics and engineering RD
issues necessary for early realization of fusion
power plant. Preliminary RDs, such as advanced
SC magnets, low activation structural materials,
blanket for DEMO plant will also be performed.
Information Exchange, Conceptual Design Studies,
preliminary RD
Design of Fusion Power Plant
JapanSSTR?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
10o
102
104
106
10-2
10-4
Year
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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
Ip5.5MA, Bt2.76T, Rp2.97m, a1.13m Superconduc
ting Tokamak
Based on Joint Report of EU/JA Expert Gr.
Meeting 18-19 April 2004, Culham on BA for Fusion
Power
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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 Syste
m 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
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BA Projects leading to construction of DEMO
10years
10years
10years
Performance Extension
Construction
Basic Performance
Decom.
ITER Project
Test of Breeding Blanket Module
Remote ExperimentationDistributed Coordination
BA
IFMIF
Construction
BA
IFMIF-EVEDA
Operation
Fusion Power Plant Tech. Coordination Center
Conceptual Design Study PhysicsTechnology RD
BA
EDA RD
Construction
Operation
BA
Computer Simulation Center
Burning Plasma Simulation
Burning Physics DEMO Plasma Simulation
JAEU ITERDEMO Physics Support Activities
Upgrade of JT-60
BA
Satellite Tokamak
Commissioning
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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
Oarai Center
JAERI
Year
Main Enterprises
Formation of a solid basis for nuclear
RD Establishment of nuclear fuel cycle
technology Promotion of fusion energy RD
Kansai Institute
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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
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Fusion Research Organization in JAEA
DG M.Seki
DGM.Seki
Fusion Energy Research Directorate
Naka Fusion Institute
Facilities
Research
Office of Research Promotion
S. Seki
H. Kobayashi
ITER Project Promotion Gr
Dept. of Administration
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
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Research Plan of JT-60 in 2005
Targets

• Long sustainment of High Performance
• - ?n2-2.5 and HH1 for gt25s
• - higher bootstrap current fraction
  (IBS/Ip0.7-0.8)
• - high fusion triple product
  n?T5x1019m-3skeV for 20s
• - high H-factor in wall-saturated condition
• 2. Attainment of ?n gt3.5 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
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Long Time Sustainment of High Performance Plasmas
Target
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Installation of ferritic plates inside the VV,
completed (for wall stabilization experiments)
W ferritic plates
W/O ferritic plates
Reduction of ripple well by ferritic plates
()
8Cr2W ferritic steel (Bsat?1.8T) Thickness 23mm
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JT-60 Modification Program

• National Centralized Tokamak Device -
• Satellite Tokamak for ITER -

SC device with a break-even class
performance Sustain high beta (?N3.5-5.5)
non-inductive CD Mobility and flexibility as a DD
device Lower aspect ratio (A2.6 3.1 in
ITER) High shape factor (S7 lt5 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)
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Fusion Engineering RD 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 Accumulat
ion of neutron irradiation data for F82H Using
HFIR(ORNL) to the level over 50dpa Technical
preparations for IFMIF-EVEDA Basic Fusion
Technology Continue basic RDs 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)
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Superconducting Magnet Development
1. Preparation for ITER TF coil case procurement
2. Trial fabrication of ITER Nb3Sn strands

• 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.

• 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.

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.

Ic100A at 17.5T
Silver content was reduced by 23.
Ic120A at 17.5T
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Heating and Current Drive System
Neutral Beam (NB) system
Electron Cyclotron 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 power density
  obtained at MeV level energy

Long Pulse 170GHzGyrotron for ITER
0.5MW/100sec, 0.9MW/9sec 0.2MW/500sec (in
progress)
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ITER Test Blanket Module (TBM) Development
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.
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. 1040C
HIP Temp. 1100C followed by normalizing at 950C
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.
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Fusion Materials Development
F82H RAFMS as candidate materials for blanket
first wall

• Database up to 2030 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 (lt450C)
• IFMIF will be used to obtain database in gt50dpa
  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
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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.