TOKAMAK FOUNDATION in USSR/RUSSIA

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TOKAMAK FOUNDATION in USSR/RUSSIA

• V.P. Smirnov
• Nuclear fusion institute, RRC Kurchatov institute
• 22nd IAEA Fusion Energy Conference, Geneva, 13
  18. 10. 2008

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Content

• Start of Fusion in USSR/Russia
• Tokamaks in Kurchatov and Kurchatov
  branch/TRINITI, major steps
• Ioffe Institute
• Present status and plans

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Start of USSR Fusion programme
July 1950
Letter of Soviet soldier O.A. Lavrentiev to Stalin
January 1951
I.E. Tamm, A.D. Sakharovs proposal on toroidal
magnetic trap is approved
O.A. Lavrentiev
Leaders of Kurchatov fusion team
Toroidal systems
Z-pinch
Tokamak
Leaders of USSR fusion programme
Academician L.A. Artsimovich ? till
1973 Academician E.P. Velikhov ? after 1973
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Tokamak T-1(1958)
T-1 is the first tokamak in the world R 0.67
m, a 0.17 m, Btor 1.5 T, Ip 100 kA Smooth
metal liner without gaps Stability condition
was proved Energy losses by line emission of
ions with Z gt 1 is a main channel Radiation
losses contributes 80-90 of heating power
October 2008 50 years anniversary of Tokamak
T-1 experiment start
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To the end of 1950-es, M. A. Leontovich formed
the unique scientific school of theorists worked
in magnetic fusion and plasma physics

• Tokamak-related areas of theoretical researches
  in Kurchatov
• Tokamak plasma equilibrium
• Plasma stability (MHD, drift, kinetic)
• Transport processes
• Waves in non-uniform plasma and turbulence
• Plasma irradiation and atomic processes
• Plasma-wall interaction

?.?.Leontovich (1903-1981)
Achievements of 1950-es 1960-es were summarized
in Reviews of Plasma Physics, ed. by
M.A.Leontovich, B.B. Kadomtsev, V.D. Shafranov
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Tokamak plasma equilibrium

• Grad-Shafranov equation(V.D. Shafranov, 1957
  H. Grad, 1958)
• Shafranovs shift(V.D. Shafranov, 1959)
• D-shaped tokamak(V.D. Shafranov L.A.
  Artsimovich, 1972)

V.D. Shafranov (born in 1929)

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Other tokamak-related issues

• Cyclotron irradiation formula(B.A. Trubnikov,
  1957)
• Braginskiis transport equations (S.I.
  Braginskii, 1963)
• Neoclassical theory of transport processes(A.A.
  Galeev R.Z. Sagdeev, 1968)
• Trapped particle instability (B.B. Kadomtsev
  O.P. Pogutse, 1966)
• Kadomtsev-Pogutse-Strauss reduced eqs.(B.B.
  Kadomtsev O.P. Pogutse, 1973 H. Strauss, 1976)

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Tokamak energy balance (19591970)Metal liner
(500C preheated) ? Prad 0,3 Ploss
T-2 (1960) T-3 (1962) TM-2 (1965)
TM-3 (1970)

• Energy balance study
• Anomalous energy transport
• Te exceed Bohm prediction by 35 times
• ? is growing when Te increase
• First attempts to find a scaling low

Tokamak T-3 (1962)
R 1 m, a 0,15 m, B 3,8 T, I 150 kA
Optimistic prediction of tokamak future
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Energy confinement in tokamak overcame Bohms
prediction
T-3 and TM-3 investigations of plasma energy
balance confinement time were in 10 times more
Bohms one
Laser diagnostics approves diamagnetic
measurements
Time behavior of energy time ?E and Bohm time ?B
Tokamak winner fusion facility competition
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Tokamak plasma ohmic heating (T-3A)

• Electron temperature reached 1 keV on T-3A
  tokamak (diamagnetic measurements)
• NPA diagnostic revealed Maxwelian distribution
  function of ions
• Ion temperature reached 350 eV in accordance
  with classical expectation
• First registration of thermonuclear neutron yield
  start of fusion tokamak (1971)

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T-10 Tokamak (1975)

• The largest tokamak in 1975, R1.5 m, aL0.36 m,
  Bt up to 5?, Ip up to 0.65 ??
• Bohm diffusion theory for tokamak disproved
  finally
• Electron temperature record Te10 keV ECRH
  ?EC 4 ?W (1987)
• ECCD efficiency determination (1991)

Turbulence structure determination with 3D
(toroidal, poloidal, radial) correlation
reflectometry Nano-dust revealing under ITER
relevant energy load
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Electron Cyclotron Current Drive in T-10

• ECCD efficiency in accordance with linear theory
• ?CD0.03x1020AW-1m-2- 1st harmonic (1991)
• ?CD0.013x1020AW-1m-2-2nd harmonic(1994)
• Non inductive operation with ECCD
• O-mode(1991)
• Excellent localization for X-mode wec 1/30
• High power density up to 25Wcm-3
• Sawtooth suppression by ECCD (1994) for the first
  time

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ICRF Plasma Heating and CD

• 
  Basic practical outputs
• Tokamaks
• Ion Minority heating and
  ion-ion Hybrid resonance discovery, tokamak
  TM-1Vch
• at Kurchatov 1970-75, and
  lately on many tokamaks
• Applications
• - ion heating on on T-10,
  TFTR, JET, ITER, Ti up to 14 keV, energetic
  protons
• up to 7 MeV
• - stellarators W7-AS (magnetic
  beach scenario), LHD and mirrors
• - HFFW CD on DIII-D, NSTX and
  possibly on ITER
• - Localised MC Current Drive
  for NTM suppression

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World First Tokamak with D-shape cross-section
L.A. Artsimovich, V.D. Shafranov. Pisma v
JETPh 15, 1972, p. 7276 A.M.
Stefanovskiy. Pisma v JETPh 31, 1980, p. 663668

• Elongated plasma column equilibrium
• Vertical displacement event stabilization by
  passive and active coils
• Plasma parameters correspond to best ones of
  circular tokamak

T-8 (1976) Layout R 28 cm, a 4.8 cm,
B 0.9 T, J 24 kA, q 2.2, n 71013 cm
T-8 open way to D shape tokamak (T-9, 1977)
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Tokamak T-7
It is a first tokamak with superconductivity
solids
R 1.22 m a 0.35 m I 220 kA Btor 3.0 T
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Superconducting tokamak T-15 (1988-1995)
T-15 parameters (R 2.43 m, a 0.78 m)
Parameter Design Achieved
Toroidal magnetic field, T 3.5 3.6
Plasma current, MA 1.4 1
Pulse duration, s 5 1.5
NBI, MW 6 0.6
ECRH, MW 5 1.5
First successful demonstration of a large-scale
Nb3Sn magnet systems possibilities
Superconducting toroidal magnet (V
50m3, W 416 MJ)
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TSP (T-14) tokamak TRINITI
TSP tokamak (tokamak with strong magnetic field
and adiabatic plasma compression) was created for
achieving breakeven conditions in D-T plasma
The main design parameters of TSP tokamak
Before compression on minor radius After compression on minor radius After compression on major radius
R, m 1.06 1.06 0.415
a, m 0.32 0.2 0.128
BT, ? 2.0 5.0 12.8
ltngt, m-3 5?1019 1.3 ? 1020 8 ? 1020
I, MA 0.48 0.48 1.23
?t, ms 30 128 10
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Basic results of Ioffe institute tokamaks
1970 1975 1980
1985 1990 1995
2000 2005 2010
High density mode. Hot ion mode. H-mode. Central
plasma fuelling by plasma gun
Start
GLOBUS-M
Fast ion confinement in NBI regimes
Role of electric field in enhanced confinement
Physics of adiabatic heating
Ohmic H mode
Start
TUMAN-3M
Effective ion and electron heating by LH waves
and ITB
First observation of small scale ETG turbulence
Observation of LH ion heating due to the
parametric decay instability observed by enhanced
scattering diagnostics
FT-2
Start
Neutral Particle Analysis
T-3 experiments (passive)
T-10 experiments (active)
JET experiments (MeV range)
TFTR D-T alpha experiments
JET isotope ratio experiments
ITER NPA design
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FT-2 tokamak studies of lower hybrid heating and
current drive,small scale turbulence and
anomalous electron transport
FT-2 parameters (R  0.55m, aL  0.079m,
Ipl  22kA and Bt  2.2T, q  6)
(???  2???.180 kW, ?tLH  5ms, f  920MHz,
N?? 3)
Effective LH heating of electrons and ions
accompanied by transition to improved confinement
regime and ITB formation Ti (100eV ? 200eV)
Te (300eV ? 500eV) ltnegt (3.5
1019m-3 ? 4.5 1013cm-3) LHCD in geometry similar
to T-15M (R/r6)
Evolution of central plasma parameters at LHH
The first observation of small-scale ETG mode
instability by UHR backscattering diagnostics
The ETG mode is observed at FT-2 at wave number
qr?s  8 close to the position of the ETG mode
growth rate maximum in accordance to GS2 code
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Spherical tokamak Globus-M
Plasma jet injection into target tokamak plasma
was proposed at Globus-M as a method for central
discharge fuelling
Engineering parameters R0.36 m, a0.24 m, A1.5
Btor0.55 T, Ipl 0.3 MA, PAxH 2 MW Record
plasma parameters ltngt 1.21020m-3, ßN 6
ßT 15, ßp 0.7
Thomson measurements of ne(R) evolution
demonstrate fast two times central density
increase in 50 µs after the jet injection
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T-15 is expected to be main tokamak in Russia
till 2040 year
2009
2011
2013
2015
2017
2019
2021

ISSUE OF T-15U FINAL PROJECT, PURCHASE OF
STANDART EQUIPMENT, DEVELOPMENT OF NON-STANDART
EQUIPMENT
ASSEMBLY AND ADJUSTMENT OF EQUIPMENT
PLASMA EXPERIMENTS WITH CIRCULAR PLASMA AT
ADDITIONAL POWER HEATING 16 ?W AND PULSE
DURATION 5 S
ASSEMBLY OF DIVERTOR COILS AND IN-VESSEL
ELEMENTS. PLASMA EXPERIMENTS WITH ELONGATED
PLASMA AT ADDITIONAL POWER HEATING 20 ?W
AND PULSE DURATION 30 S
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• Main tasks of ?-15U
• creating the elongated separatrix magnetic
  configuration in existing discharge chamber
• creating of control system for elongated
  configuration equlibrium
• development, manufacturing and assembling of
  divertor system in discharge chamber
• up-grading of systems for additional plasma
  heating and current drive, an increasing of power
  heating up to 22 MW and pulse duration up to 30
  s
• - development and manufacture of control system
  for stability, equilibrium, heating and
  confinement of high temperature plasma in on-line
  regime.

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Conclusion

• Invention of tokamak and development of its
  physics and technology have provided solid
  starting base for way to fusion power plant (FPP)
• Strategy of Russian activity in fusion is aimed
  to construction of FPP about 2050
• Responding to signals from Russian fission power
  community, the activity in analysis of
  fusion-fission systems is revived. Fuel
  production and transmutation have first priory.
  Success of hybrids shall allow to introduce
  fusion in commercial use in more short time