Current Status of DiscussionCurrent Status of DiscussionCurrent Status of Discussion Current Status of Discussion on Roadmap of Fusion Energy on Roadmap of Fusion Energy

Research and Development in JapanResearch and Development in Japan

H.YamadaH.Yamada

National Institute for Fusion Science

AcknowledgementA.Komori (NIFS) Y.Kamada (JAEA), K.Itoh (NIFS),A.Komori (NIFS) Y.Kamada (JAEA), K.Itoh (NIFS), M.Enoeda(JAEA), S.Konishi (Kyoto Univ.),

International WorkshopInternational WorkshopMFE Roadmapping in the ITER Era

Princeton, 7-10 Sep., 2011

Three major critical issuesThree major critical issues

1 Society’s observation of fusion has dramatically

Three major critical issuesThree major critical issues

1. Society s observation of fusion has dramatically changed since the accident of the Fukushima Dai-ichi nuclear power stationnuclear power station

2. Current Japanese policy requires a certain2. Current Japanese policy requires a certaineconomical feasibility in DEMO

3. Definition of DEMO is critical for decision What is the role of the first DEMO in Japan ?

2/25

Structure of decision making and executionStructure of decision making and execution

Cabinet Office

Science and Technology Basic Plan

Council for Science Technology Policy (CSTP)Science and Technology Basic Plan (every 5 year)

Japan Atomic Energy Commission (JAEC)Promotion plan of fusion R&D issued in 2005

Ministry of Education, Culture, Sports, Science and Technology (MEXT)

Science and Technology Basic PlanCouncil for Science and Technology

- Working Group for Fusion Research

National Institute for Fusion Science

Japan Atomic Energy Agency

(JAEA)Universitiesfor Fusion Science

(NIFS)(JAEA)

programmatic approach academic approachi t ti f b tt it t

p g ppunder governmental decision integration of bottom-up commitment

from universities3/25

4th Science and Technology Basic Plan 20114th Science and Technology Basic Plan 2011--2015 by CSTP2015 by CSTP Original document before the Fukushima Dai-ichi accident

Exploration of ocean, telecommunication, space transportation and satellite,new energy atomic energy of fast breeder reactor and fusion highnew energy, atomic energy of fast breeder reactor and fusion, high-performance computing, global positioning system, information security should be promoted from the aspect of national security and fundamental

ti l t h lnational technology

Revised document after the Fukushima Dai-ichi accidentR&D for safety, prevention of disaster, proliferation and nuclear security of atomic energy should be greatly reinforced.

R&D of technology for atomic energy such as a fast breeder reactor should be conducted in line with the energy policy and the atomic energy policy.

R&D f f i h ld b t d ith tt ti t i t ith thR&D of fusion should be promoted with attention to consistency with the energy policy and the atomic energy policy, at the same time, its characteristics and the status of R&D.

“Safety” becomes a much more important key-word than beforeDi i “A t f f i ” h b j t l h dDiscussion on “Assessment of fusion energy” has been just launchedin the Japan Society of Plasma and Fusion Research

4/25

Roadmap of Fusion DevelopmentRoadmap of Fusion Developmentin Promotion Plan of Fusion R&D by JAEC issued in 2005

3rd phaseSci. & tech. feasibility

2nd phaseScientific

4th phaseTech. demonstration

aliz

atio

n

Commer-cialize

demonstration Econ. feasibility

mm

erci

a

Decision ; whether it is right or wrong to build a DEMO ?

ITER DEMO

com to build a DEMO ?

JT-60

ITER h i R&D I t f t k k l Thnt

JT-60 JT-60SA

ITER R&DDevelopment of reactor eng. (material, blanket, etc.)

IFMIF (i di ti f ilit )

ITER physics R&D, Improvement of tokamak plasma, Theory

elop

men

Development

ITER eng. R&DSafety assessment, Conceptual & eng. design of DEMO

IFMIF (irradiation facility)

deve

DevelopmentFusion science

emic LHD (helical system)Basic research of plasma science (small & med exp theory)

acad

Basic research of reactor eng. (advanced material, blanket, reactor design, etc.)

Basic research of plasma science (small & med. exp., theory)

5/25

Requirements for DEMORequirements for DEMO,

whatever form is chosenin Promotion Plan of Fusion R&D by JAEC issued in 2005

1. Demonstrate power generation by technology which

can be used in practical implementation

2. Incorporate the projection of a certain economical

feasibility for practical implementationfeasibility for practical implementation

6/25

Points in Check & Review in Fusion R&D 1. Points in Check & Review in Fusion R&D 1.

Issues Criterion in decision to the 4th phase

in Promotion Plan of Fusion R&D by JAEC issued in 2005

1. Demonstration of burning control under the self-heating

Demonstration of Q20 for several 100 seconds and burning control in ITER

2. Demonstration of non-inductive steady state operation

Demonstration of non-inductive current-driven plasma with Q5 for 1 000 seconds ininductive steady state operation

with Q5driven plasma with Q5 for 1,000 seconds in ITER

3 Establishment of integrated Establishment of integrated technology3. Establishment of integrated technology

Establishment of integrated technology through operation and maintenance of ITER, and confirmation of safety technology

4. Establishment of high-beta steady-state operation to make

Achievement of steady-state operation with high-beta collisionless plasma (n=3.5-5.5) in

a projection of economical feasibility

JT-60 SA and so on.

7/25

Points in Check & Review in Fusion R&D 2. Points in Check & Review in Fusion R&D 2. in Promotion Plan of Fusion R&D by JAEC issued in 2005

Issues Criterion in decision to the 4th phase

5 R&D of material and reactor Demonstration of breeding and retrieval of

in Promotion Plan of Fusion R&D by JAEC issued in 2005

5. R&D of material and reactortechnology for DEMO

Demonstration of breeding and retrieval of tritium, heat removal, power generation of blanket in DT experiment in ITER Completion of validation of irradiation data for low-activation ferritic steel up to 80 dpa

6. Conceptual design of DEMO Completion of conceptual design of DEMO consistent with developed fusion plasma and

t t h lreactor technologyVV

Water Cooled Ceramic Breeder proposed by JapanTest Blanket Module(TBM)

Plasma

Water Loop

G

Structure of RAFM (F82H)

Neutron Production of

(TBM)

Plasma Generato

1700mm MultiplierPebble Bed (Be)

fusion fuel tritium Extraction of energyr

600mm500mm

Tritium BreederPebble Bed (Li2TiO3)

gy

courtesy of Dr.M.Enoeda 8/25

Strategic Convergence and Development of Fusion ExperimentsStrategic Convergence and Development of Fusion Experiments

Steady High sma

Stateg

Performance

ite p

las

y to

ign

Steady State

HighPerformance di

fficu

lty

StatePerformance ddifficulty to sustain plasma

Keys for early realization of DEMO(1) Demonstration and control of burning plasma ITER

difficulty to sustain plasma

(1) Demonstration and control of burning plasma ITER(2) Steady state operation

JT-60SA : non-inductive current drive at high with minimizing circulation powercirculation power

LHD : high performance plasma to convince us of burning 9/25

Magnetic Confinement FusionMagnetic Confinement FusionTokamak Helical system

Plasma current = 0

Intrinsically 3-D, Steady-state

Plasma current > 10 million amperes

Approximately 2-D, Transient y , yDevices: LHD, W7-X(Germany) , NCSX

Share large commonality as well as contrast

pp y ,Devices: ITER, JT-60SA, etc..

Share large commonality as well as contrast accelerate establishment of scientific basement

for rational decision of DEMO in slightly over a decadeg y

10/25

Reduction of circulating power is criticalReduction of circulating power is criticalJapan EU

Reactor design Slim-CS (innovative)

PPCS-A (conventional)

PPCS-D(innovative)(innovative) (conventional) (innovative)

Plasma current 17 MA 31 MA 14 MAFraction of self-generated 75 % 45 % 76 %g

current 75 % 45 % 76 %

Generated electric power 1.2 GW 2.1 GW 1.1 GWEl t i i d fElectric power required for

current drive 0.14 GW 0.93 GW 0.15 GW

Circulating power tolerable large tolerable

Fusion powerElectric power to the grid

Note: Efficiency of electric power conversion is assumed to be 50 %

Generator

Current drive to be 50 % achievement = 20 %

Ch i f bl k t i th iti l i t

Current drive

Choice of blanket is another critical point:ex. Pump in the case of He cooling

11/25

JT-60SA Project Conducted under the BA Satellite Tokamak Programme

by EU and Japan, and the Japanese National Programme. P j t i i Project missions

Support exploitation of ITER Complement ITER with resolving key physics

and engineering issues for DEMO reactors.A fully superconducting, highly shaped tokamak capable ofconfining break-even equivalent class deuterium plasmas lastingconfining break-even equivalent class deuterium plasmas lastingfor a duration (typically 100s) longer than the timescalescharacterizing the key plasma processes with high heating power41MW

5

6

JT-60SA TargetDEMO reactor

41MW.

4

3

JT-60SA Target reactors

ITER N

JT 60U Steady-state JT-60SA should pursue full

1

2ITER Existing

Tokamaks

JT-60U Steady state

Inductive

pnon-inductive steady-state

operations with high N (> no-wall ideal MHD stability limits)

Sustainment Time (s)

00 300040010020 40 60 80

wall ideal MHD stability limits). courtesy ofDr.Y.Kamada 12/25

JT-60SA device has been designed in order to satisfy the central research needs for ITER and DEMO

for ITER

the central research needs for ITER and DEMO

H-mode / Pedestal / ELM (incl. RMP, pellet, … )Local Ripple & TBM TestWall Heat Load

p / a

Bt

ram

eter

Disruption & mitigation etc. ( database, control tech. : Intensive Gas puff ….)

Integrated control S=q

95I p

hape

Par

Integrated control( operation scenarios, plasma actuators,diagnostics …)

RED: Superconducting

Sh

for DEMOHigh beta high bootstrap steady-state

f CS Big portsReplaceableRequirements for CSHeat & particle controllability in steady-stateControl of Highly self-regulating plasmas

Big portsfor EngineeringR&D

Replaceable Divertor(<15MW/m2)

Needs for DEMO commissioningDivertor concept testsBlanket, first wall material tests

W660H1830Blanket, first wall material tests

etc.

courtesy of Dr.Y.Kamada 13/25

JT-60SA Plasma Regimes for ITER & DEMOITER & DEMO-relevant Regimes :

Non-dimensional Parameters & Integrated Performance

‘Simultaneous & steady-state sustainment of the key performances required for DEMO’key performances required for DEMO (= highly self regulating) has never been achieved the goal of JT-60SA.

Decide the practically acceptable DEMOparameters (phys. & engineering).

D l & d t t ti l t fDevelop & demonstrate a practical set ofDEMO plasma controls.

courtesy of Dr.Y.Kamada 14/25

JT-60SA: Status of ProcurementsB 2011 J l 15 P t A t (PA ) h b l d dBy 2011 July, 15 Procurement Arrangements (PAs) have been concluded(JA: 8PAs, EU: 7PAs) = 70% of the total cost of BA Satellite Tokamak Program.

PF Coil Manufacture Building &PF Conductor Manufacture Building

SC Conductor with length of 500 m for EF Coil

Superconductor double pancakes for EFManufacture Building EF Coil pancakes for EF

Material forMaterial for V.V.

Trial production Prototype of VV and

Building for Vacuum vessel JT-60SA

The first VV 40 degree sectorp

of VV outboard 20 deg

VV and welding test

acuu essesector assembly

Research Plan V2.1

courtesy of Dr.Y.Kamada 15/25

JT-60 Torus Disassembly Th fi t i f di bl f di ti t d l f i d i i J

Neutron Shield 2010 Mar. 2010 Sep. 2011 Mar.10th.

The first experience of disassembly of radio-activated large fusion device in Japan

N-NB 2012 S

~ 1 month delayEarthquake

Power Supply

2009 Oct.2011 April

SummerDisassembly Restarted

Power Supplyremoval

2011 Aug.

Cryostat Base from EUcourtesy of Dr.Y.Kamada 16/25

Large Helical Device ProjectLarge Helical Device Project

The world largest helical system Intrinsic advantage and engineering capability of steady-state operation Complementary/alternative role to tokamak approachThe goal of the LHD project Establish scientific basement for a helical DEMO reactor

H.YamadaNational Institute for Fusion Science プラズマ若手夏の学校

平成22年8月11日 六甲スカイヴィラ

Establish scientific basement for a helical DEMO reactor Comprehend physics of toroidal plasmas

17/25

LHD has worked very well for 13 yearsLHD has worked very well for 13 years Operation for 13 years engineering base of a large-scale superconducting and

i t f f i t d l t

Heating capabilityNBI 29 MW

< LHD basic dimension >

cryogenic system for fusion reactor development ECH 3.5 MWICH 2 MW

• Outer diameter 13.5 m• Cold mass 820 ton• Total weight 1500 tong• Magnetic field 3 T• Magnetic energy 0.77 GJ

Several-month-long operation, 14 times since 1998• Operational time of He pcompressor : 65,000 hours

Duty = 99.1 %• Coil excitation number Coil excitation number

: 1,400 times• Plasma discharges

: 107 000 shots: 107,000 shots A large number of opportunitiesfor diversified collaboration on physics

18/25

Progress of plasma parameters is Progress of plasma parameters is very encouragingvery encouragingvery encouraging very encouraging

Long pulse : >1keV plasma for 1 hourQuasi-steady state high beta

%)

Long pulse : 1keV plasma for 1 hour

High beta : plasma kinetic pressure

pressureof magnetic field

LHD

LHD (%

<> = 5.1 % at B = 0.425 T<> 5 % is maintained

p essu eof magnetic field

Tokamak

sus/E

5 % is maintained for > 100 energy confinement time E

High density

Tokamak

ne(0) = 1.21021m-3

1.5 atmospheric pressure at B = 2.5 T an innovative concept of

Very high density operation

1.0

1020

/m3 )

Tokam ak

an innovative concept of ignition at T(0) = 6-7 keV

High ion temperaturen e

exp

(1

D IIIA lcator C

PBX

g o te pe atu eTi = 6.4 keV at ne = 1.61019m-3

accompanied phenomena to expel i iti

nescal (1020 /m 3)

0.1 1.0 100.1

PBXimpurities

nGW(1020/m3) 19/25

Machine capability is planned to be Machine capability is planned to be maximized in a coming few yearsmaximized in a coming few yearsmaximized in a coming few yearsmaximized in a coming few years

1. Upgrade of heating power2. Closed helical divertor3. Deuterium experiment

CY 2011 2012 2013 2014JFY 2011 2012 2013 2014

Exp. Camp. 15th 16th 17th 18th

NBITangential 16 MW ←

NBIPerpendicular 13 MW ← →18 MW

ECHMax 3.5MW 4.5MW 6 MW

ECHCW 0.5MW 0.8MW 1 MW

ICHMax 2 MW 3 MW 6 MW

ICHCW 1 MW 1.5 MW 3 MW

DivertorBaffle & Dome 2/10 8/10 →10/10

DivertorCryo-pump 0/10 6/10 →10/10

20/25

How can we approach comprehensive understanding ?How can we approach comprehensive understanding ?2-D and 3-D are not in a binary opposition !2 D and 3 D are not in a binary opposition !

3-D effect, which dissolves in 2-D, appears as the outcome when the constraints due to 2-D degeneracy are lifted.

3-D physicsDIII-D with RMP

LHD

ITER with TF and TBM

2-D physicsIt is an over simplified approach to assume that 3-D effects are complexity specific to 3-D machines and 3-D magnetic fields. 21/25

33--D Effects in D Effects in ToroidalToroidal PlasmaPlasma

Mean flow Neoclassical transport

Transport

3-D effectsViscosity

Zonal flow Turbulent transport3 D effects

in helical systemand tokamak

transport

(with RMP)

Topology

Magnetic island Mode locking

Topology

Stochastic mag. field ELM controlMHD stability

3-D equilibrium and transport are determined self-consistently3 D equilibrium and transport are determined self consistently

22/25

Fusion Eng. Research Project has startedFusion Eng. Research Project has startedtowards steadytowards steady--state helical DEMO reactorstate helical DEMO reactor

2011 2016 2022 2036FY2027

Conceptual design Basic designStep by step advancement of reactor design

yy

Improved basic designp g g p g

Full-scale, full-condition testingEstablishment of

i i bengineering base

Large-scale high-field superconducting magnet

Engineeringdesignsuperconducting magnet

Long-life liquid blanket With i iti

Construction

design

Licensing

Hi h h t fl l

Low activation structural materials

universities

OperationHigh heat flux plasma facing wall

Tritium control

p

Tritium control

23/25

Physics of plasmas/non-equilibrium systemTa Panta rhei (everything flows): Thorough investigation of dynamism and turbulence

Based on “Scientific Road Map” (by Section III, Science Council of Japan)

Ta Panta rhei (everything flows): Thorough investigation of dynamism and turbulence

ever

y ow

s” non-equilibrium statistical

mechanics

plasmaphysics

gy aw o

f “e

thin

g flo

law of econo-physics

Creating viewof nature

AcademicCreation physics

of life development

law of turbulent physics

hnol

og Lat physics

turbulence/chaos/rhythm

non-equilibrium

systemglobal turbulent transport theory

Euler turbulencesolution of singularity

equation plasma

development

d Te

ch confinementof high-

temperature plasma

soft matter

bio-function

equation of state

Eflopscomput.

plasmaaccelerator

ce a

nd plasmaphotonicdevice

plasmabeam

nonlinearsolvable

economy

fracturee-science

ITER

Sci

enc

nonlinearexcitation

AGN:NGC 4261model plasma

confinementdevices

S

lineardispersion

Scientific Innovation

2010 2020 2030 2040courtesy of Prof. S.-I.Itoh, and Prof. K.Itoh 24/25

Approaches to resolve major critical issuesApproaches to resolve major critical issues

1. Society’s observation of fusion has dramatically h d i th F k hi D i i hi id tchanged since the Fukushima Dai-ichi accident

Assessment of safety, efforts to get support from society and self definition should be emphasizedsociety and self-definition should be emphasized and accelerated much more than before.

2. Current Japanese policy requires a certain economical feasibility in DEMO Demonstration of steady-state high-performance

plasma relevant to DEMO by LHD and JT-60SA

3. Definition of DEMO is critical for decision What is the role of DEMO ?

ITER,…, DEMO -2, DEMO -1, DEMO 0, DEMO + 1,..S Stimulate intensive discussions on multiple levels with outcome of this WS 25/25