2010年12月26日

“核能核技术概论”之核能核技术概论 之

聚变与高温等离子体物理聚变与高温等离子体物理

高 喆

工物馆158 or 新工物馆903

gaozhe@tsinghua.edu.cn

SUNIST Laboratory &Plasma Science and Fusion Laboratory

Fusion is simpleFusion is simple

Fusion is simple but importantFusion is simple, but important

Can we bottle the sun on sun on the earth?

A. S. Eddington（1882-1944）

Probably a best solution to Energy & E i t blEnvironment problem

Abundant (104 year for D T limited by Lithium resources)Abundant (104 year for D-T, limited by Lithium resources)Clean (no warm-room air, no high activation )Safe (inherent safrty, no explosion risk )

But the problem is it is too difficult But, the problem is…it is too difficult

Single fusion reaction: easyFusion energy: not easy

~0.4MeV, It seems so easy?

Fusion for ENERGY requires the confinementof high temperature plasmaof high temperature plasma

Lawson criterion （1957）Lawson criterion （1957）

Fusion power nTPnTPP brbrf33

transport

Power loss

brbrf

radiation

P b kPower back

For D-T, Power gain>Power loss gives

n E > 1020 (m-3 .s)For D-T, Power gain>Power loss gives

Considering Ti~10-20keV，the requirement of the triple product is Considering Ti~10-20keV，the requirement of the triple product is

John D. Lawson1923-2008

of the triple-product is

n E Ti > 1021 (m-3 s keV)of the triple-product is

How to confine the high T plasma to achieve n > 1020 m-3 s ? achieve n E > 1020 m-3 s ?

Sun flare:Long lifetime of plasma along the Magnetic field

Longer confinement timeLonger confinement time

Higher densityICF but not confinement

G it ti C fi tGravitation Confinement

The physics of magnetic confinement plasmaThe physics of magnetic confinement plasma

We need a geometry! We need a geometry! Plasma

Linear system

Toroidal system

Magnetic coilField line线圈But

Toroidal system

But,“鱼与熊掌不可兼得”or “there is no free lunch”

磁力线

A clear idea: StellaratorA clear idea: Stellarator

Lyman Spitzer, Jr. (1914—1997)Lyman Spitzer, Jr. (1914 1997)

LHD @ Japan

W7 AS @ GW7-AS @ Germany

But it seems a little bit complicated!But，it seems a little bit complicated!

NCSX (expected in 07 but shutdown in 08)

In principle，what we need is just the t ti t frotation transform

Field line

Coils

Field line

Tokamak（the winner）Tokamak（the winner）

I. Tamm(1895-1971)

A. Sakharov(1921-1989)

Noble prize in Physics 1958Noble prize in Peace 1975

TOKAMAK (M d i U S S R)

Lev Artsimovich(1909-1973)

TOKAMAK (Made in U.S.S.R)=“toroidal”+“kamera”+“magnit”+“kotushka”

Joint Europe Torus

HL 2A@SWIP Ch dHL-2A@SWIP,Chengdu EAST@ASIPP,Hefei

I t ti l Th l E i t l R tInternational Thermonuclear Experimental Reactor

Evolution of the Shape Evolution of the Shape

E t d t th t f S h i l T k k Extend to the concept of Spherical Tokamak

START(1990-1998)START(1990 1998)

Evolution of the confinement mode, which determines the size of the reactor which determines the size of the reactor

Understand some but not enough Understand some, but not enough

Turbulence transport

collisional transport

Shear flow decorrelationShear flow decorrelation

till d d th i t l li lso still depends on the experimental scaling law

AUG JETAUG JET

ITER

Even the scaling law is not availablenot available

0.93 0.15 0.41 0.69 1.97 0.58 0.78 0.19,98 2 190.0562th y p t L aI B n P R M

Other important issues on high T plasma：H ti d C t D iHeating and Current Drive

PΩ=I2R ∝B2/T3/2

is not enough

9m9m

15m 5m

M t h d d i St bilitMagneto-hydro-dynamics Stability

EC ray

St bilit d di ti

NTM control @ ASDEX-U ELM @ MAST

Stability and disruption simulation @GA

Ed h iEdge physics

Super-X Divertor

E i i d t i l bl Engineering and material problem

Talk more about ITER

Overall Project Costs

Construction Cost: 4584.7 kIUA

RF(9%)CN

(9%)Construction Cost: 4584.7 kIUA

Total procurement value: 3569.2 kIUA

Staff: 935.5 kIUA

European Union (46%)

(9%)

KO(9%)

JAR&D: 80 kIUA

Overall contingency: 115.3 kIUA

JA(9%)

IN(9%) US

(9%)Total amount: 4700 kIUA (7047 Mil € / 2008 )

Operations Cost for 20 years: 188 kIUA / year

(9%)

Deactivation and Decommissioning: 281+530 kIUA

IUA: ITER Units of AccountKIUA = one million US $ in 1998

Mission of the ITER ITERIgnitionMission of the ITER

Physics:

IgnitionBreak Even

Physics:• ITER is designed to produce a plasma dominated by

-particle heatingp g

• produce a significant fusion power amplification factor

(Q ≥10) in long-pulse operation (300 - 500s)

• aim to achieve steady-state operation of a tokamak (Q=5)

• retain the possibility of exploring ‘controlled ignition’(Q≥30)

Technology:• demonstrate integrated operation of technologies for

a fusion power plant

• test components required for a fusion power plant

• test concepts for a tritium breeding module• test concepts for a tritium breeding module

ITER > 10 21

Extrapolation

JET TFTR-3s k

ev)

JET, TFTRJT-60U

E(1

020m

-

~ 10 20~21

n i T

iτ E

~ 10 19~20

ASDEXEAST etc.n

T3T3,HT-7 etc. ≤ 10 19

n T τni TiτE(m-3 s kev)

Practical energy resources should be SSO !!

Pf i ∝ n﹡T﹡τE ＞ 10 21 m-3﹡s﹡kevPfusion n T τE ＞ 10 m s kev

S d S O i (SSO)Steady-State Operation (SSO)

Fi l G l E ∝ ( n T τ ) tFinal Goal Efusion∝ ( n × T ×τE ) × t burning

ITER于05年12月15日在法国C d h 动工ITER于05年12月15日在法国Cadarache动工

ITER“Permis de Construire”

Start Tokamak Assembly

First PlasmaUpdated Schedule Complete

Tokamak Core Construction

2007 2008 2009 2010 2011 2012 2013 2014 2015 2016 2017 2018 2019 2020

ITER Construire Assembly

Tokamak Basic Machine

ITER Construction

Construction

Tokamak Basic Machine

Issue TF Coils PAs 1st TF Coil at Site Last TF Coil at Site

Issue PF Coil PAs 1st PF Coil at Site Last PF Coil at Site

Issue VV PAs 1st VV Sector at Site Last VV Sector at Site

Buildings & Site

Tokamak Complex Excavations

Tokamak Building Construction

Site Leveling

Tokamak Bldg 11 RFETendering process

Tokamak AssemblyTokamak Basic Machine Assembly

Ex Vessel AssemblyStart Install CS Start Cryostat Closure

Start Assemble VV

2018 First PlasmaMinimal internal vessel components

In Vessel AssemblyStart Torus Pump Down

Pump Down & Integrated Commissioning

Current Date .Change assembly—Alternative Schedule: “scenario one”;

First Plasma Nominal Plasma Hydrogen-Helium Complete Start DT Q=10 Long Pulse Achieved

Overview of Operation up to DT

2019 2020 2021 2022 2023 2024 2025 2026 2027 2028 2029ITER Construction

Assembly Phases II and III

2030 2031 2032

ITER OperationsIntegrated Commissioning

Assembly Phase 2Assembly Phase 3

g g

H d H li O ti C i

Start Torus Pump Down

Pump Down & Integrated Commissioning

Magnet Commissioning

Hydrogen-Helium Operations Campaign

Commission, Cool & Vacuum

Plasma Development & H&CD CommissioningFull H&CD, TBM & Diagnostics Commissioning

Deuterium Operations Campaign

Pre-Nuclear Shutdown & Divertor Change

Q=10 Short Pulse

Start DT

Deuterium Operations

Planned ShutdownStart DT

Deuterium-Tritium Operations Campaign

Q=10 Long Pulse Achieved

J Jacquinot, FEC 2008J Jacquinot, FEC 2008

1026 watts, 0.01 W/m3

J Jacquinot, Geneva FEC 2008 41JJ OCS Cannes 17 March 08415×108 watts, 5×105 W/m3

“ITER” means “way” in Latin. It is, indeed, the way to fusion energy although it is probably full of thorns (in Plasma Physics and Fusion related Engineering)Engineering) .

I ti l C fi t F i Inertial Confinement Fusion

Direct drive and Indirect drive Direct-drive and Indirect-drive

X-rays enhance implosion symmetry and reduce hydrodynamic instability at a cost in efficiency

Central hot spot ignition and Fast Ignition Central hot spot ignition and Fast Ignition

Fast Ignition is an approach to ICF which decouples compression from ignition and maydecouples compression from ignition and may relax the requirement of laser energy.

Progress of Laser-ICFProgress of Laser-ICF

215m*120m（Target room: R~10m）

National Ignition Facility (USA):215m 120m（Target room: R 10m）192*351nm Laser，1.8MJ，3ns，500TW

N ti l I iti F ilit (USA)National Ignition Facility (USA)

Design: ‘94~’97 about 1 billion $Design: 94 97 about 1 billion $ 09 finished, about 4 billion $

Mission:• National Security• Energy for the Future• Energy for the Future• Understanding the Universe

Implosion physics: i l l l i t timainly laser-plasma interaction

Comparing to MCF plasma physics: highly nonlinear, but with simple geometryComparing to MCF plasma physics: highly nonlinear, but with simple geometry

Also, big challenging on laser engineering and plasma Physics

Other interesting but doubtful attemptsOther interesting but doubtful attempts

Cold FusionCold Fusion阴极:钯

阴极 铂

Stanley Pons and Martin Fleischmann

阴极:铂

Stanley Pons and Martin Fleischmann Mar. 21,1989 99.5%D2O+0.5H2

O%+少量LiDHProbs: thermal vs neutrongamma vs neutrongamma vs neutroncomparative experiment

DOE Conlusion：“did not present convincing evidence that useful sources of energy would result from phenomena attributed to cold fusion”

now renamed Chemically enhanced nuclear reaction

muon fusionmuon fusionlifetime of μ: 2.2×10-6s

for 100 fusion reactionG i 2GEnergy Gain：2GeV

Energy Lost：10GeV (by accelerator)

Hope：the catalytic efficiency of μ

Bubble fusion

R.Taleyarkhan, Science 2002

C i t M ’ LComparing to Moore’s Law

Y l k ti !You are a lucky generation!

Still needgreat efforts on PLASMA Phys.PLASMA Phys.

& FUSION Tech.

聚变与等离子体相关课程：聚变与等离子体相关课程：

《等离子体物理基础》《等离子体物理基础》《聚变能引论》*

《等离 物 论》

本科

《等离子体物理导论》《高温等离子体物理》《气体与等离子体动理论》

研究生

《气体与等离子体动理论》《磁约束聚变工程基础》*《高温等离子体物理诊断》《高温等离子体物理诊断》

主要授课老师：高喆、蒲以康、王文浩等有系列实验*有系列实验

本PPT使用了来自互联网的大量未注明引用的材料，仅用于清华大学《核能核技术概论》课程教学使用，谢绝传播。

Copyrights of all of the materials from the internet belong to original authors. This lecture

t l d i th l f I t d ti note only used in the classroom of Introduction to nuclear technology and nuclear energy atTsinghua University Tsinghua University.

Homework：

1. 简单推导聚变用于能源应用对等离子体参数提出的要求(即Lawson判据)。2. 如果实现只利用欧姆加热达到托卡马克等离子体点火？(你需要考虑能量约束时间

与磁场的定标关系，最大电流与约束磁场的关系，电阻与温度的关系。)3. 调研ITER和NIF计划，它们在等离子体参数及相应关注的等离子体物理问题上有什么差别？

你有什么想法去解决聚变研究缺乏阶段性应用的困境4. 你有什么想法去解决聚变研究缺乏阶段性应用的困境？

2011年2月28日0 00之前将作业交到 h @ il 或者新系馆报箱2011年2月28日0：00之前将作业交到 zhegao@gmail.com 或者新系馆报箱

Attit d i E thi ！Attitude is Everything！