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Current Status of urrent Status of Nuclear Fusion Development Nuclear Fusion Development Focusing on Focusing on the the Tokamak Concept Tokamak Concept Yong Su Na Yong Su Na Yong-Su Na Yong-Su Na 17 September 2008 17 September 2008 17 September , 2008 17 September , 2008
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Page 1: Current Status of Nuclear Fusion Development Focusing on ...ocw.snu.ac.kr/sites/default/files/NOTE/4203.pdf · Current Status of Nuclear Fusion Development Focusing on Focusing on

CCurrent Status of urrent Status of Nuclear Fusion Development Nuclear Fusion Development pp

Focusing on Focusing on the the Tokamak ConceptTokamak Concept

Yong Su NaYong Su NaYong-Su NaYong-Su Na

17 September 200817 September 200817 September, 200817 September, 2008

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ContentsContents

II Wh t i l f i ?Wh t i l f i ?II What is nuclear fusion? What is nuclear fusion?

IIII How to confine the hot sun?How to confine the hot sun?

IIIIII How to heat the plasma?How to heat the plasma?

IVIV What is the current status?What is the current status?

VV What are the critical issues?What are the critical issues?VV What are the critical issues?What are the critical issues?

VIVI What is the future of fusion?What is the future of fusion?

VIIVII Closing remarksClosing remarks

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What is nuclear fusion?

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Nuclear Fusion Reaction

4

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Nuclear Fusion Reaction

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Origin of the Star Energy

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Origin of the Star Energy

Th l f iThermonuclear fusion

7

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Utilisation of the Fusion Energy

A Mark-17 Hydrogen bomb atA Mark-17 Hydrogen bomb at the National Atomic Museum

Peaceful use of the fusion energy?8

Peaceful use of the fusion energy?

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Peaceful Use of the Fusion Energy

• Lithium in one laptop battery + half a bath-full of ordinary water (≥ one egg cup full of heavy water) = 200 MW

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Build a Sun on the Earth

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How to confine the hot sun?

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Confinement

12

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Gravitational Confinement

The sunBlack hole

13

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Inertial Confinement

Fusion fuel microcapsule (microballoon)(microballoon)

14

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Spiderman II15

Spiderman II

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Magnetic Confinement

• Imitation of the Sun on Earth

gravitationmagnetic field

plasmapressure

plasma pressure

Equilibrium in the sun Plasma on earthmuch much smaller & tiny mass!

16

much, much smaller & tiny mass!

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Plasma – The 4th State of Matter

Increasing Temperature The 4th stateof matter

17

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Plasma – The 4th State of Matter

Ions and electrons are separatedIons and electrons are separated.

18

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Magnetic Confinement

M tiMagneticfield

19

ion

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Magnetic Confinement

El tElectron

Magnetic field

20

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Magnetic Confinement

M tiMagneticfield

21

ion

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Magnetic Confinement

M tiMagneticfield

22

ion

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Magnetic Confinement

M tiMagneticfield

Mirror Machine

old Hanbit Device in NFRIold Hanbit Device in NFRI

23

ion

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Magnetic Confinement

M tiMagneticfield

24

ion

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Magnetic Confinement

M tiMagneticfield

25

ion

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Confinement of the Plasma

R0 a

Donut-shaped vacuum vessel

26

R0 = 1.8 m, a = 0.5 m in KSTAR

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Confinement of the Plasma

Plasma needs to be confined

27

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Confinement of the Plasma

Toroidal Field (TF) coil

Applying toroidal magnetic field

28

3.5T in KSTAR

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Confinement of the Plasma

Toroidal Field (TF) coil

ion

Applying toroidal magnetic field

29

3.5T in KSTAR

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Confinement of the Plasma

B∇

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Confinement of the Plasma

ion+++

B∇

- - -electron

31

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Confinement of the Plasma

ion+++

l t ielectricfield E

- - -electron

32

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Confinement of the Plasma

ion+++ ExB drift

l t ielectricfield E

- - -electron

ExB drift

33

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Confinement of the Plasma

ion+++ ExB drift

l t ielectricfield E

- - -electron

ExB drift

Poloidal field should be applied

34

Poloidal field should be appliedThen, how to?

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Confinement of the Plasma

ion+++ ExB drift

l t ielectricfield E

- - -electron

ExB drift

Poloidal field should be applied

35

Poloidal field should be appliedDrive the plasma current !

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Confinement of the Plasma

Central Solenoid (CS)as a primary circuit

d∫ ⋅−= s dsB

dtdv

Faraday‘s law

36

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Confinement of the Plasma

Central Solenoid (CS)as a primary circuit

d∫ ⋅−= s dsB

dtdv

T f

Faraday‘s law

Transformer

37

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Confinement of the Plasma

Central Solenoid (CS)as a primary circuit

Plasma currentas a secondary circuit

T fTransformer

38

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Confinement of the Plasma

Central Solenoid (CS)

Poloidal fieldinduced by the plasma

current

Plasma currentinduced by CS

T fTransformer

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Confinement of the Plasma

currentcurrent currentcurrent

coil coilT fTransformer

40

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Confinement of the Plasma

currentcurrent currentcurrent

Force

coil coilT fTransformer

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Confinement of the Plasma

X PF coilsPlasma

current ●

X

currentcurrent

X

ForceForce

XForce

X

PFil

plasma●

coil

Plasma shaping by PF coils

42

XPlasma shaping by PF coils

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Confinement of the Plasma

Central Solenoid (CS)

Poloidal fieldinduced by the plasma

current

Plasma currentinduced by CS

Plasma shaping byPlasma shaping byvertical field

coils (PF)

43

coils (PF)

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TokamakInvented by Tamm and Sakharov in 1952

44

Toroidalnaja kamera magnitnaja katushka(Toroidal chamber magnetic coil)

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Tokamak

JET (Joint European Torus): R0 = 3 m, a = 0.9 m, 1983-today

45

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Tokamak

JET (Joint European Torus): R0 = 3 m, a = 0.9 m, 1983-today

46

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TokamakKSTAR (Korea Superconducting Tokamak Advanced Research):

R0=1.8m, a=0.5m, 2008-today

47

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Fusion Power Plant System

BlanketNeutron(14 MeV)

Coolant

Deuterium

Tritium

Lithium

48Tritium

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Blanket

Blanket Functions:A P E t tiA. Power Extraction

– Convert kinetic energy of neutrons and secondary gamma rays into heat– Absorb plasma radiation on the first wallp– Extract the heat (at high temperature, for energy conversion)

B. Tritium Breeding– Tritium breeding, extraction, and control– Must have lithium in some form for tritium breeding

C Physical Boundary for the Plasma (First wall)C. Physical Boundary for the Plasma (First wall)– Physical boundary surrounding the plasma, inside the vacuum vessel– Provide access for plasma heating, fueling– Must be compatible with plasma operation– Innovative blanket concepts can improve plasma stability and confinement

D R di ti Shi ldi f th V V lD. Radiation Shielding of the Vacuum Vessel

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Fusion Power Plant System

Burning plasma

Power conversionsystemy

Fusion reactor system

Heat transfer & l l 50Fuel cycle system

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How to heat the plasma?

51

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Plasma Heating

Heating with:Heating with:ohmic currentsfast particles

52

pmicrowaves

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Plasma Heating – Neutral Beam Injection (NBI)

Injection of a beam of neutralB-field

Injection of a beam of neutralfuel atoms (H, D, T)

at high energies (Eb > 50 keV)

H,D,T⇓Ionisation in the plasma

⇓Beam particles confinedBeam particles confined

⇓Collisional slowing down

53

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Plasma Heating – Wave (ICRH, ECRH, LHH)

Tuning forkTuning fork

54

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Plasma Heating – Wave (ICRH, ECRH, LHH)

Tuning forkTuning fork

Resonance

55

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Plasma Heating – Wave (ICRH, ECRH, LHH)

Excitation of plasma wave Resonance

zone(frequency w) near plasma edge

⇓Antenna

⇓wave transports power into the plasma center

⇓absorption near resonanceabsorption near resonance,

e.g. ω ≈ Ωc ,i.e. conversion of wave energy into ki i f i l Bkinetic energy of resonant particles

mqB

c =Ω

Ω=ω⇓

56

RcΩ=ω⇓

Resonant particles thermalize.

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What is the current status?

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Fusion Performance

• What is required to light a fire in a stove?What is required to light a fire in a stove?

Fuel: D, T

n,

Amount/density

Heat insulation

TDeuterium

Heat insulation

Ignition temperature

?≥τTnTritium

?≥⋅⋅ τTnCriterion (Lawson)

required

58

q

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Status of the Tokamak Research

59

Q = Pfus/Pext

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Status of the Tokamak Research

• Progress in fusion can be compared with the development of computer chips and particleof computer chips and particle physics accelerator energy.

• Present machines produce significant fusion power:- TFTR (USA) 10 MW (1994) - JET (EU) 16 MW (Q=0.7) (1997)

60

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What are the critical issues?

61

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Critical Issues on the Fusion Development

power dispersion

Hi h F i P MaterialHigh Fusion Power

Continuous operation

High plant efficiency

High fuel purity

Tritium treatment

62

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How to increase the fusion power?the fusion power?

63

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Stabilisation of Plasma Turbulence

• Turbulence stabilisation → Increase of plasma pressure → High fusion power

Z Z Internal Transport Barrier

→ High fusion power

Z Internal Transport Barrier

Temperature profile

R RC t li f l t i t ti l C t li f l t i t ti l

Temperature profile

64

Contour lines of electric potential. Contour lines of electric potential.

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Stabilisation of Plasma Turbulence

65

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Suppression of Plasma Instabilities

• Suppression of Neoclassical Tearing Mode by ECCD

66

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Edge Region Instability and Disruption

Disruption

Edge Localised Mode

67

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Suppression of ELMs

• S i f ELM b h li l fi ld DIII D

68

• Suppression of ELMs by helical field on DIII-D

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Why high radiation required?What are material issues?What are material issues?

69

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Plasma–Wall interactions

• Hi h h t fl t th di t i l

70

• High heat flux to the surrounding materials

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Radiation Induced by Impurity Seeding

• Heat flux to materials reduced by radiation emission

71

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Radioactivation of Materials

• Neutron impacts on materials

72

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What is the future of fusion?

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Status of the Tokamak Research

ITER

74

Q = Pfus/Pext

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Status of the Tokamak Research

Fusion power plant -------------------------------Goal ITER ----------------

• Progress in fusion can be compared with the development of computer chips and particleof computer chips and particle physics accelerator energy.

• Present machines produce significant fusion power:- TFTR (USA) 10 MW (1994) - JET (EU) 16 MW (Q=0.7) (1997)

75

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ITER Project

• International Thermonuclear Experimental Reactor - “the way” in Latinthe way in Latin- the essential next step in the development of fusion

• Objective - To demonstrate the scientific and technological feasibility of fusion power.

• The world’s biggest international research project

76

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Fusion Energy Development

• The Fast Track Approach

77

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KSTAR Project• Korea Superconducting Tokamak Advanced Research

- superconducting tokamak using ITER-relevant magnets- capability of reactor-relevant plasma performances

• Objective - To integrate optimised plasma performance and continuous

78

operation as a step toward an attractive tokamak fusion reactor

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Korean Plan for Fusion Energy Development

2030년대

상용화2020년대 중반

DEMO2015년 DEMO

2007년 이후

KSTAR

2015년

ITER-- 대용량대용량 전기생산전기생산

-- 실질적인실질적인 발전발전 실현실현

-- 고성능고성능, , 고효율고효율장시간장시간 운전연구운전연구

-- 연료연료 연구연구-- 열이용열이용 연구연구-- 재료재료 연구연구-- 공학공학 연구연구

-- 실질적인실질적인 발전발전 실현실현-- 시스템시스템 최적화최적화-- 경제성경제성 구현구현

공학공학 연구연구

79

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SummarySummary

II Wh t i l f i ?Wh t i l f i ?II What is nuclear fusion? What is nuclear fusion?

IIII How to confine the hot sun?How to confine the hot sun?

IIIIII How to heat the plasma?How to heat the plasma?

IVIV What is the current status?What is the current status?

VV What are the critical issues?What are the critical issues?VV What are the critical issues?What are the critical issues?

VIVI What is the future of fusion?What is the future of fusion?

VIIVII Closing remarksClosing remarks

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When he was asked how long it would take to build the firstWhen he was asked how long it would take to build the first fusion power plant, the Soviet physicist Lev Artsimovich – one of the pioneers of tokamak research – replied that “fusion will be there when society needs it.” That time is fast approaching, and with the construction of ITER finally about to start, efforts are now gearing up for the longer –term prospect of fusionare now gearing up for the longer term prospect of fusion energy.

- “Fusion: the way ahead, Physics World March 2006

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“The entire cost of the fusion development programme is equal to only a week ofprogramme is equal to only a week of spending in the international energy markets ”markets.”

I Cook IAEA 2005- I. Cook, IAEA 2005