International West Lake Symposium on Fusion Plasma Physics 2011 Jinlin Xie on behalf of KTX team...
-
Upload
annabella-pitts -
Category
Documents
-
view
216 -
download
3
Transcript of International West Lake Symposium on Fusion Plasma Physics 2011 Jinlin Xie on behalf of KTX team...
International West Lake Symposium on Fusion Plasma Physics 2011
Jinlin Xie on behalf of KTX team
Dept. of Modern Physics, School of Physical Sciences
University of Science and Technology of China
Hefei, Anhui, China
New possible RFP project in China
Keda Torus eXperiment (KTX)
Outline
Motivation of the new RFP program in China
– Energy diversity: Fusion is necessary for China
– Fusion diversity: Toroidal Alternate Configuration
The KTX program in USTC
– The emergence of KTX
– The KTX concept design
– The Goals and Scientific Issues for KTX
China Tops U.S. in Energy Use
“Asian Giant Emerges as No. 1 Consumer of Power, Reshaping Oil Markets, Diplomacy.”
-The Wall Street Journal JULY 18, 2010
Coal: 70% Oil: 20% Hydroelectric sources: 6% Natural gas: 3% Nuclear power: 1%
We need an effort to diversify our energy supplies!
Nuclear fusion — the process that powers the sun, offers an environmentally benign, intrinsically safe energy source with an abundant supply of low-cost fuel.
China’s energy consumption requirements
Diversity during the early days in China fusion progam (starting from 1958):
Z pinch, Ө pinch, FRC, reversed field pinch
Focus, mirror device
Stellarator
Tokamak
An early stellarator in China
Stellarator “LinYun”: designed in1965, capacitor bank energy: 800kJ plus ICRF heating
Stellarator “LinYun”: designed in1965, capacitor bank energy: 800kJ plus ICRF heating
Tokamaks in China
SouthWestern Institute of PhysicsHL-2A at SWIP
Huazhong University of Science & TechJoint-TEXT at HUST
Institute of Plasma Physics Chinese Academy of Sciences
EAST & HT-7 at ASIPP
University of Science and Technology of China (USTC)
Qinghua University ST: SUNIST
Current Fusion research platforms in China
Currently, four Tokamaks are running in ASIPP, SWIP and HUST respectively. Fusion program in China is focusing on Tokamak research. The tradition of diversified fusion research has been lost!
China needs RFP research program It is not as yet clear which configuration will ultimately lead
to the most attractive fusion reactor – Diversity is part of the nature, so is fusion research. – Ancient Chinese philosophy “Let a hundred schools of thought contend” (BC 770)
Five scientific and technical research areas– Burning Plasmas in ITER– Creating Predictable, High-performance, Steady-State Plasmas– Taming the Plasma-Material Interface– Harnessing Fusion Power
– Optimizing the Magnetic configuration No related projects (issue 5th) have been launched in China
fusion program
Ref: Report of the Research Needs Workshop (ReNeW), Bethesda, Maryland – June 8-12, 2009; Report of the FESAC toroidal alternates panel, November 26, 2008
Reversed Field Pinch: an important toroidal alternate concept
Tokamak RFP
Three major configurations of MCF Stellarator: magnetic field is generated totally by the external coils
Tokamak: magnetic field is generated primarily by the external coils
RFP: magnetic field is generated primarily by the plasma current
Main advantages of RFP: Reversed Field Pinch Small externally applied field:
the use of normal magnets, high engineering beta, high mass-power-density, efficient assembly
The safety factor q<1, higher helical twist, enhanced magnetic shear
Large plasma current density: Ohmic heating for a burning plasma
Fascinating phenomena of magnetic self-organization and nonlinear plasma physics:
test bed for the understanding derived at high field, good platform to investigate the transport, link between the fusion energy science and astrophysics
TITAN an RFP reactor 1990 VS. ITER
TITAN ITER
TITA
NITER
Major radius(m) 3.9 6.2
Minor radius(m) 0.6 2.0
Plasma current(MA) 18 15
Toroidal field(T) 0.36 5.3
Energy-confinement time(s) 0.15 5.8
Poloidal Beta 23% 3%
Fusion Power(GW) 2.3 0.5
Neutron wall load(MW/m2) 18 0.5
Present RFP experiments
RFX-Mod (Italy)RFX-Mod (Italy)R/a = 2 m / 0.46 mR/a = 2 m / 0.46 m
MST (UW-Madison)MST (UW-Madison)R/a = 1.5 m / 0.5mR/a = 1.5 m / 0.5m
Extrap-T2R (Sweden)Extrap-T2R (Sweden)R/a = 1.24 m / 0.18mR/a = 1.24 m / 0.18m
RELAX (Japan)RELAX (Japan)R/a = 0.5 m / 0.25mR/a = 0.5 m / 0.25m
RFX-Mod @ Italy• Plasma current~2MA, the biggest RFP device,
Active feedback control, high current operation MST @ U.S.
• One of the four major MCF devices, plasma current ~0.8MA, current drive & confinement improvement
Extrap-T2R @ Sweden• Active feedback control of the MHD modes
Relax @ Japan • Smale aspect ratio R/a~2
MST: improved confinement achieved via modification of the current profile
RFX: self-organized Single Helical Axis state come with electron transport barriers
Recent achievements in RFP
The RFP proposal in USTC Keda Torus eXperiment (KTX)
In USTC, We have kept fusion research, small-scale but steadily growing, for almost forty years– Tokamak physics and diagnostic– Fundamental research in small devices: magnetic reconnection experiment,
chaos, turbulence…– Space plasma research: data analysis and numerical simulation of
reconnection phenomena…
– Theory and numerical simulation: tearing mode, kink mode RFP naturally fits our current status
– The diversity of Chinese fusion research• KTX will not only address the relative important scientific issues of Tokamak,
but also improve the understanding of toroidal confinement in general
– The richness of physics: dynamo, magnetic self organization, RWM– Training of fusion talents is the priority of university
• The easy operation, compared with Tokamak; daily running
The KTX project is a nature extension of China MCF program!
The former RFP research in China
Construction from 1985 running from 1989Shutdown in 1997
R=0.48m, a=0.1mair core
Al shell: d=1cmstainless steel liner: d=0.4mm
plasma pulse < 2ms, Ip~150kA(max)Te~100eV
The first RFP device in China :SWIP-RFP
Concept design of Keda Torus eXperiment
Major radius: 1.4 m
Minor radius: 0.4 m
Aspect ratio 3.5
Wall thickness: 6 mm (stainless steel)1.5mm (copper shell)
Plasma current: 0.5 MA / 1MA
Plasma Pulse: 10 ~ 30 ms 100ms (with feedback)
Loop Voltage: 10 ~ 50 VPlasma
inductance: ~ 4 μH
Poloidal flux: 5 V٠S
Te: 600 ~ 800 eV
Plasma density (1 ~ 2) 1019m-3
Ohmic heating coils
Toroidal coilsEquilibrium coils
Modular shell: Stainless steel for vacuum chamber (6mm/2ms), plus one thin copper layer (1.5mm /20ms)
Active control configuration in KTX RWM control methods
– thick layer with good conductivity, act as an ideal conductive shell
– Rotation to suppress the RWM mode; need to control the plasma rotation or metal
wall rotation
– Active feedback with External coils: open loop & closed loop
T2
R C
oil system
(s)T
2R
Coil syste
m(s)
toroidal direction
pol
oid
al d
irec
tion
Active coils: twice the width of the sensor coils 4 (poloidal) x 16 (toroidal) positions 50% surface coverage
top
inboard
outboard
bottom
Br sensor coils 4 (poloidal) x 64 (toroidal) positionsfull surface coverage (limited acquisition)
343.125˚ 0˚ 16.875˚ 39.375˚ 61.875˚ 84.375˚
The unique features of KTX
The advanced RFP device
– Significant parameters
– advanced real-time feedback control
– Thin shell: close proximity to the plasma • Linear stability for m=0 tearing could be critical (sensitive to wall proximity)
– Optimized aspect ratio for the realization of SHAs (single helical mode), also good for the research of scaling of RFP confinement
– Optimized coil configuration for potential research of OFCD & PPCD
– Stainless steel inwall: good if accommodates advanced plasma-facing materials, e.g., lithium
– Part of the Vacuum chamber can be moved out: to ensure the maximum accessibility to interior
The Goals and Scientific Issues for KTX
Reconnection in space physicsThe disk momentum transport problem
ITER & Tokamak related– RWM in high Beta; stochastic magnetic
field & active MHD control; high beta tokamak mode with low toroidal field
Fundamental issues in space & astrophysics– Dynamo, magnetic resonnection, anomalous ion
heating, momentum transport
Training talents for MCF program– Rich physics of RFP, easy operation, daily
running, direct impression of MCF research
Ohmic coils: minimize stray field
R(m)
The distribution of the poloidal magnetic field (Green circle: the cross section a=0.4mBlue dot circle: area occupied by plasma, with a radius of 0.3m )
Gauss
Collaborated with EAST team
Vacuum field of equilibrium coils (Bvertical)Equilibrium Magnetic Surface
Ip Li betap
Rmaxis
Rout Rgapi Rgapo
500 kA
1.33 0.36 1.42 m
1.398 m
2.4 mm
6.2 mm
The milestones of KTX project We have tried to seek an appropriate experimental platform for high-temperature
plasma research for almost 10 years.– Spherical Tokamak, Stellarater(CHS), FRC, RFP
2009 Nov, Atalanta, U.S. – discussion about the possibility of RFP with Piero and Weixing during the APS meeting
2010 April, RFX, Padova, Italy– the 14th Workshop of the International Energy Agency Implementing Agreement on RFP– The concept design of KTX (thick shell)– The first literation of USTC RFP project, with RFX group, John (MST), Sadao (Relax), James
(Extrap-T2R) and Weixing, Chijin.
2010 August, MST, Madison, U.S.– The name of USTC RFP project: KTX– The second literation of USTC RFP project, with MST group, Weixing, Chijing and RFX members
(via video conference): change from thick shell to thin shell
2010 October, USTC, Hefei, China– USTC international RFP workshop, including MST, RFX, Relax members
2011 June, USTC, Hefei, China: issues of construction, with MST, Relax & EAST group
2010 April, Padova, Italy the 14th Workshop of the IEA on RFP
2010 Oct, Int RFP workshop, USTC
The RFP family is growing and thus welcomed a delegation from USTC, one of the top Chinese universities, is planning to construct a new RFP device. The new RFP will contribute towards meeting the need for a strong research program on alternate concepts, which is considered essential for the success of the Chinese domestic fusion programme in the ITER era.
2010 August, MST, Madison, U.S
Future of KTX
天时– Right time, ITER era
地利– Right place, USTC, Hefei, close to other MCF facilities
人和– Human harmonic environment
– Support from international RFP community and domestic MCF community
Conclusion: KTX must have a bright futureConclusion: KTX must have a bright future