Effects of plasma heating on the magnitude and distribution of plasma flows in the helical divertor of the Uragan-3M torsatron
Recently, a strong up-down asymmetry in the poloidal distributions of diverted plasma flows has been observed in the l = 3/m = 9 Uragan-3M torsatron, in many features similar to what have been observed in the l = 2 Heliotron E heliotron/torsatron. With this asymmetry, the predominant outflow of the...
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Національний науковий центр «Харківський фізико-технічний інститут» НАН України
2002
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Цитувати: | Effects of plasma heating on the magnitude and distribution of plasma flows in the helical divertor of the Uragan-3M torsatron / V.V. Chechkin, L.I. Grigor’eva, E.L. Sorokovoy, M.S. Smirnova, A.S. Slavnyj, E.D. Volkov, N.I. Nazarov, S.A. Tsybenko, A.V. Lozin, A.P. Litvinov, V.G. Konovalov, V.N. Bondarenko, A.Ye. Kulaga, Yu.K. Mironov, S. Masuzaki, K. Yamazaki // Вопросы атомной науки и техники. — 2002. — № 4. — С. 48-50. — Бібліогр.: 5 назв. — англ. |
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irk-123456789-802622015-04-15T03:02:01Z Effects of plasma heating on the magnitude and distribution of plasma flows in the helical divertor of the Uragan-3M torsatron Chechkin, V.V. Grigor’eva, L.I. Sorokovoy, E.L. Smirnova, M.S. Slavnyj, A.S. Volkov, E.D. Nazarov, N.I. Tsybenko, S.A. Lozin, A.V. Litvinov, A.P. Konovalov, V.G. Bondarenko, V.N. Kulaga, A.Ye. Mironov, Yu.K. Masuzaki, S. Yamazaki, K. Magnetic confinement Recently, a strong up-down asymmetry in the poloidal distributions of diverted plasma flows has been observed in the l = 3/m = 9 Uragan-3M torsatron, in many features similar to what have been observed in the l = 2 Heliotron E heliotron/torsatron. With this asymmetry, the predominant outflow of the diverted plasma is directed with the ion toroidal drift. On this basis, the asymmetry can be related to the space non-uniformity of the charged particle loss. In the work reported, the magnitude of divertor flow in U-3M and the vertical asymmetry in its distribution are studied as functions of the heating parameter P/, P being the power absorbed in the plasma, and are juxtaposed with corresponding P-related changes in the density and fast ion content in the plasma. As P/ increases, an increase of fast ion content and of particle loss, on the one hand, and an increase of divertor flow magnitude and of vertical asymmetry of the flow, on the other hand, are observed. A mutual accordance between these processes validates the hypothesis on a dominating role of fast particle loss in formation of vertical asymmetry of divertor flows in helical devices. 2002 Article Effects of plasma heating on the magnitude and distribution of plasma flows in the helical divertor of the Uragan-3M torsatron / V.V. Chechkin, L.I. Grigor’eva, E.L. Sorokovoy, M.S. Smirnova, A.S. Slavnyj, E.D. Volkov, N.I. Nazarov, S.A. Tsybenko, A.V. Lozin, A.P. Litvinov, V.G. Konovalov, V.N. Bondarenko, A.Ye. Kulaga, Yu.K. Mironov, S. Masuzaki, K. Yamazaki // Вопросы атомной науки и техники. — 2002. — № 4. — С. 48-50. — Бібліогр.: 5 назв. — англ. 1562-6016 PACS: 52.55.Fa; 52.55.Rk http://dspace.nbuv.gov.ua/handle/123456789/80262 en Вопросы атомной науки и техники Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
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Digital Library of Periodicals of National Academy of Sciences of Ukraine |
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DSpace DC |
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topic |
Magnetic confinement Magnetic confinement |
spellingShingle |
Magnetic confinement Magnetic confinement Chechkin, V.V. Grigor’eva, L.I. Sorokovoy, E.L. Smirnova, M.S. Slavnyj, A.S. Volkov, E.D. Nazarov, N.I. Tsybenko, S.A. Lozin, A.V. Litvinov, A.P. Konovalov, V.G. Bondarenko, V.N. Kulaga, A.Ye. Mironov, Yu.K. Masuzaki, S. Yamazaki, K. Effects of plasma heating on the magnitude and distribution of plasma flows in the helical divertor of the Uragan-3M torsatron Вопросы атомной науки и техники |
description |
Recently, a strong up-down asymmetry in the poloidal distributions of diverted plasma flows has been observed in the l = 3/m = 9 Uragan-3M torsatron, in many features similar to what have been observed in the l = 2 Heliotron E heliotron/torsatron. With this asymmetry, the predominant outflow of the diverted plasma is directed with the ion toroidal drift. On this basis, the asymmetry can be related to the space non-uniformity of the charged particle loss. In the work reported, the magnitude of divertor flow in U-3M and the vertical asymmetry in its distribution are studied as functions of the heating parameter P/, P being the power absorbed in the plasma, and are juxtaposed with corresponding P-related changes in the density and fast ion content in the plasma. As P/ increases, an increase of fast ion content and of particle loss, on the one hand, and an increase of divertor flow magnitude and of vertical asymmetry of the flow, on the other hand, are observed. A mutual accordance between these processes validates the hypothesis on a dominating role of fast particle loss in formation of vertical asymmetry of divertor flows in helical devices. |
format |
Article |
author |
Chechkin, V.V. Grigor’eva, L.I. Sorokovoy, E.L. Smirnova, M.S. Slavnyj, A.S. Volkov, E.D. Nazarov, N.I. Tsybenko, S.A. Lozin, A.V. Litvinov, A.P. Konovalov, V.G. Bondarenko, V.N. Kulaga, A.Ye. Mironov, Yu.K. Masuzaki, S. Yamazaki, K. |
author_facet |
Chechkin, V.V. Grigor’eva, L.I. Sorokovoy, E.L. Smirnova, M.S. Slavnyj, A.S. Volkov, E.D. Nazarov, N.I. Tsybenko, S.A. Lozin, A.V. Litvinov, A.P. Konovalov, V.G. Bondarenko, V.N. Kulaga, A.Ye. Mironov, Yu.K. Masuzaki, S. Yamazaki, K. |
author_sort |
Chechkin, V.V. |
title |
Effects of plasma heating on the magnitude and distribution of plasma flows in the helical divertor of the Uragan-3M torsatron |
title_short |
Effects of plasma heating on the magnitude and distribution of plasma flows in the helical divertor of the Uragan-3M torsatron |
title_full |
Effects of plasma heating on the magnitude and distribution of plasma flows in the helical divertor of the Uragan-3M torsatron |
title_fullStr |
Effects of plasma heating on the magnitude and distribution of plasma flows in the helical divertor of the Uragan-3M torsatron |
title_full_unstemmed |
Effects of plasma heating on the magnitude and distribution of plasma flows in the helical divertor of the Uragan-3M torsatron |
title_sort |
effects of plasma heating on the magnitude and distribution of plasma flows in the helical divertor of the uragan-3m torsatron |
publisher |
Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
publishDate |
2002 |
topic_facet |
Magnetic confinement |
url |
http://dspace.nbuv.gov.ua/handle/123456789/80262 |
citation_txt |
Effects of plasma heating on the magnitude and distribution of plasma flows in the helical divertor of the Uragan-3M torsatron / V.V. Chechkin, L.I. Grigor’eva, E.L. Sorokovoy, M.S. Smirnova, A.S. Slavnyj, E.D. Volkov, N.I. Nazarov, S.A. Tsybenko, A.V. Lozin, A.P. Litvinov, V.G. Konovalov, V.N. Bondarenko, A.Ye. Kulaga, Yu.K. Mironov, S. Masuzaki, K. Yamazaki // Вопросы атомной науки и техники. — 2002. — № 4. — С. 48-50. — Бібліогр.: 5 назв. — англ. |
series |
Вопросы атомной науки и техники |
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fulltext |
EFFECTS OF PLASMA HEATING ON THE MAGNITUDE AND
DISTRIBUTION OF PLASMA FLOWS IN THE HELICAL DIVERTOR OF
THE URAGAN-3M TORSATRON
V.V. Chechkin, L.I. Grigor’eva, E.L. Sorokovoy, M.S. Smirnova, A.S. Slavnyj, E.D. Volkov,
N.I. Nazarov, S.A.Tsybenko, A.V. Lozin, A.P. Litvinov, V.G. Konovalov, V.N. Bondarenko,
A.Ye. Kulaga, Yu.K. Mironov, S. Masuzaki∗, K. Yamazaki∗
Institute of Plasma Physics, National Science Center “Kharkov Institute of Physics and
Technology”, Akademicheskaya st. 1, 61108 Kharkov, Ukraine
∗National Institute for Fusion Science, Oroshi-cho 322-6, Toki-shi 509-5292, Japan
Recently, a strong up-down asymmetry in the poloidal distributions of diverted plasma flows has been observed in
the l = 3/m = 9 Uragan-3M torsatron, in many features similar to what have been observed in the l = 2 Heliotron E
heliotron/torsatron. With this asymmetry, the predominant outflow of the diverted plasma is directed with the ion
toroidal drift. On this basis, the asymmetry can be related to the space non-uniformity of the charged particle loss. In
the work reported, the magnitude of divertor flow in U-3M and the vertical asymmetry in its distribution are studied as
functions of the heating parameter P/ en , P being the power absorbed in the plasma, and are juxtaposed with
corresponding P-related changes in the density en and fast ion content in the plasma. As P/ en increases, an increase
of fast ion content and of particle loss, on the one hand, and an increase of divertor flow magnitude and of vertical
asymmetry of the flow, on the other hand, are observed. A mutual accordance between these processes validates the
hypothesis on a dominating role of fast particle loss in formation of vertical asymmetry of divertor flows in helical
devices.
PACS: 52.55.Fa; 52.55.Rk
1. INTRODUCTION
Experimental studies of spatial distributions of plasma
flows in the natural helical divertor of the l = 2 Heliotron
E (H-E) heliotron/torsatron with NBI and ECH have
shown [1,2] that a strong vertical asymmetry of these
distributions is possible in helical devices. This
conclusion has been confirmed by measurements of
plasma flow distributions in the helical divertor of the l =
3 Uragan-3M (U-3M) torsatron with RF heated plasmas
[3]. In many characteristics, the asymmetries in H-E and
U-3M are similar, despite a substantial difference of these
devices in magnetic configuration, plasma heating
methods and plasma parameters, this being an indication
of universality of this effect. Recently, some
manifestations of vertical asymmetry in the distribution of
diverted plasma parameters have been also revealed in the
l = 1 Heliotron J device with a helical magnetic axis [4].
The existence of many-fold difference in the values of
particle and energy fluxes to symmetrically positioned
target plates can raise serious problems with the heat
removal in future helical devices of ITER scale.
Therefore, a search for the nature of divertor flow
asymmetry should become an important issue of divertor
research.
With magnetic field reversal in U-3M, the larger
divertor flux is always observed on the ion toroidal drift
side. On these grounds it is supposed [3] that a substantial
contribution to the asymmetry is made by those fast ions,
which are trapped into helical magnetic field ripple wells
and, not “filling” the rotational transform, left the
confinement volume due to the non-compensated toroidal
drift [5]. Such a possibility has been confirmed by the
results of calculations of angular distribution of particle
direct loss in U-3M [3].
The objective of this work is to find out a possible link
between plasma heating in U-3M and the magnitude of
divertor flow and the asymmetry of its distribution. In the
studies reported, a qualitative correlation has been found
between the heating power, the rate of particle loss and
fast ion content, on the one hand, and the magnitude of
divertor flow and degree of its vertical asymmetry, on the
other hand.
2. EXPERIMENTAL CONDITIONS
In the l = 3/m = 9 U-3М torsatron (Ro = 1 m, a ∼ 0.1
m, ι( a ) ≈ 0.4) an open helical divertor is realized. The
magnetic field Bφ = 0.7 T is generated by the helical coils
only. A hydrogen plasma is RF produced and heated (ω ≤
ωci). The line-averaged electron density en can attain ∼
1019 m-3. The RF power P absorbed in the plasma attains
240 kW in the 50 ms pulse.
The diverted plasma is detected by 78 plane 1.25×0.8
cm2 Langmuir probes. Six probe arrays are arranged
poloidally in the spacings between the helical coils in two
half-field-period separated symmetric poloidal cross-
sections of the torus φ = 00 (A-A) and φ = 200 (D-D) as is
shown in Fig. 1. The gap between the plates in an array
(0.1 cm) is much less than the plate size in the polodal
direction (1.25 cm).
Two operating regimes are used specified by the
pressure of hydrogen admitted continuously into the
vacuum vessel. In the “lower pressure regime” (LPR,
units 10-5 Torr), the plasma occurs at P ≈ 80 kW. The
level of quasi-steady state density en is determined by
the balance between ionization of the gas entering the
confinement volume and plasma escape. At P ≈ 80 kW
en takes (2.5÷1.5)×1018 m-3. As P increases, en
gradually falls up to (1.0÷0.7)×1018 m-3 at P ≈ 240 kW
(Fig. 2). The existence of a heating-related plasma loss is
also evidenced by a short-time en rise occurring after RF
pulse switched off (Fig. 2, inset).
48 Problems of Atomic Science and Technology. 2002. № 4. Series: Plasma Physics (7). P. 48-50
80 120 160 200 240
1.0
1.5
2.0
2.5
0
1
2
3
0 20 40 60 80
1
2
3
, 1
0
m
_ e
18
-3
I
R
F
time, ms
de
ns
ity
,
1
0
m
_
e
18
-3
RF power , kW
, a
.u
.
n n
P
120 140 160 180 200 220 240
0
1
2
3
4
5
6
7
8
9
10
P,
I
/n
,
1575 eV
450 eV
135 eV
n
_ e
kW
re
l.
un
its
1 3 5 7 9 11 13 15 17
0
5
10
15
20
0
5
13579111315
I s,
m
A
N
I s,
m
A
TOP
BOTTOM
N
A-A
Fig. 1. Disposition of Langmuir probe arrays in the
symmetric poloidal cross-sections A-A and D-D. Shown
are the helical coils I, II, III and the calculated edge
structure of the magnetic field. The probe numbering of
interest in A-A: top spacing, 1-17; bottom spacing, 1-15.
in D-D: top spacing, 1-9; bottom spacing, 1-8.
Fig. 2. Quasi-steady
state line-averaged
electron density en as
a function of absorbed
RF power P at a fixed
hydrogen pressure. In
the inset, time traces of
RF current in the
antenna IRF (envelope)
and density en .
In the “higher pressure regime” (HPR, units 10-4
Torr,), en attains (7÷10)×1018 m-3. When studying the
power dependence of divertor flow magnitude, both ion
saturation current Is and P are normalized by en . In LPR,
the range of P/ en values (30÷320) kW/1018 m-3 is
covered. In HPR, P/ en can be reduced up to ∼10 kW/1018
m-3.
With P ≈ 240 kW in LPR, the ECE-estimated electron
temperature attains Te(0) ≈ 300÷400 eV, while it does not
exceed 20 eV in HPR.
The energy spectrum (ES) of plasma ions as measured
by an CX neutral energy analyzer oriented normally to the
torus midplane is distinguished by a slowly decaying high
energy tail. For P/ en = 300 kW/1018 m-3 a “perpendicular
temperature” of Ti1 ∼60 eV can be assigned to the
majority (∼90%) of ions. Also, two minor groups of faster
ions with “temperatures” Ti2 ≈ 326 eV and Ti3 ≈ 900 eV
can be conventionally separated. The presence of the Ti1
and Ti2 groups is confirmed by the form of CV 227,1 nm
profile. The high energy tail also remains for lower P/ en .
However, as P increases, the relative content of low
energy ions (Ti1 group) does not change appreciably,
while that of higher energy ions grows, with the growth
rate increasing with energy (Fig. 3).
Fig. 3. Relative
contents In/ en of ions
with three fixed
energies as functions
of heating power P.
The heating related behavior of en and ion energy
can cause to a great extent the pecularities, which are
observed in the behavior of diverted plasma during the
heating.
3. EFFECTS OF PLASMA HEATING ON
DIVERTOR FLOWS
The effect of plasma heating on the magnitude and
spatial distribution of diverted plasma flows in the
symmetric cross-sections A-A and D-D is displayed most
clearly in the flows, entering the top and bottom spacings
between the helical coils. As an example, the polodal
distributions of these flows are shown in Fig. 4 (A-A) as
Fig. 4. Ion saturation
current Is vs probe
number N in the top and
bottom spacings
between the helicalcoils
in the poloidal cross-
section A-A.
Is(N) plots taken in LPR with P ≈ 240 kW and Bφ directed
counterclockwise. The higher maxima at the top and
bottom belong to the divertor legs located closer to the
major axis. The Is maxima in symmetric legs are several
times different at the top and bottom, with the larger flow
being directed upward, i.e., with the ion B×∇B drift.
In Fig. 5 presented are Is/ en (maximum values) vs
P/ en plots for the top and bottom spacings in A-A. The
data for both LPR (○) and HPR (●) are used. The same
plots for D-D have a similar form. In both cross-sections
Is/ en tends to grow with P/ en on the ion toroidal drift
side. The maximum Is/ en values are comparatively close
at the top and bottom for the smallest P/ en values,
49
A-A
II
I
II
III
φ = 2 0 o
φ = 0
o
1
17
9
1
BOTTOM
OUTBOARD
8
1
1
23
40
40
-40
40
-40
40
cm
cm
cm
cm
INBOARD
BOTTOM
TOP
III
D-D
TOP
-40
I-40
6
1
1
15
0 100 200 300
0
5
10
/ , kW/10 mPne
18 -3
as
ym
m
et
ry
in
de
x,
D-D
A-A
_
3 12 21 30 39 48 57 66 75 84 93
7
14
21
28
35
42
49
56
63
70
77
ion energy, 10 eV
de
ns
ity
, 1
0
c
m
11
-3
ν
b
pl
sb
Fig. 5. Maximum values of en - normalized ion
saturation current Is vs heating parameter P/ en in the
top and bottom spacings between the helical coils in the
poloidal cross-section A-A.
10 – 20 kW/1018 m-3, their ratio α not exceeding ∼2. As P/
en increases, the flow grows more rapidly at the top, and
α can attain ∼10 for P/ en ∼ 300 kW/1018 m-3. The same
holds for D-D. Thus, the degree of vertical asymmetry of
divertor flows is a rising function of heating power
(Fig. 6).
Fig. 6. The asymmetry index α as a function of heating
parameter P/ en in the poloidal cross-sections A-A and
D-D. The lower pressure regime.
4. SUMMARY AND DISCUSSION
In summary, the following processes are observed at
the same time as the absorbed RF power increases.
In the confinement volume:
- charged particle loss increases; this is displayed in a
reduction of quasi-steady state value of en (Fig. 2);
- relative fast ion content increases, with the growth
rate being a rising function of ion energy (Fig. 3).
In the divertor region:
- the total flow of diverted plasma increases (Fig. 5);
- a predominant rise of the diverted plasma flow in the
ion toroidal drift direction, with the asymmetry index α
rising with power (Fig. 6).
In view of ideas having been developed in [3], the
following causality can be suggested for the processes
observed. The heating power increase results in a rise of
fast ion relative content (Fig. 3). Due to a poor
confinement of these particles, particle loss increases and
the density en decreases (Fig. 2), on the one hand, while
the diverted plasma flow increases (Fig. 5), on the other
hand. A dominating contribution to the particle loss is
made by those fast banana ions, which become trapped
into the helical ripple wells and leave the confinement
volume due to the toroidal drift. Therefore, a dominating
rise is undergone by plasma flows in the top spacings
between the helical coils (Fig. 5). In turn, this results in a
rise of vertical asymmetry of divertor flow (Fig. 6).
The range of P/ en values used in these studies allows
to cover a wide range of characteristic collision
frequencies, which govern the character of charged
particle loss from the confinement volume (Fig. 7). In the
higher density discharges (small P/ en , ● in Fig. 5)
predominant orbit losses are limited by the plato (pl) or
banana (b) diffusion and, therefore, the asymmetry of
divertor flow is small. With P rise and en decrease, the
diffusion regime of ion-ion collisions shifts into the
region of lower frequencies with higher transport
coefficients. Since the diffusion in the velocity space is of
stochastic character in its nature, it results in a uniform
scattering of particles in the co-ordinate space. Therefore,
the rise of diffusion (non-direct) ion loss can lead to only
total value of the divertor flow increase without changing
its asymmetry. In the lower density discharges (large P/
en , ○ in Fig. 5), the diffusion in the 1/ν collisional regime
typical for most of >250 eV ions, does not prevent the
banana ions to be trapped into helical ripple wells. As a
result, a considerable fraction of these particles enters the
divertor region in the upper half of the torus, increasing
the vertical asymmetry of the divertor flow.
Fig. 7. Ion-ion
collision time vs
density and ion
energy. The
boundaries of
corresponding
diffusion regimes
are indicated by
bold lines.
This work was carried out in collaboration with NIFS
(Toki, Japan) by the Program LIME
REFERENCES
[1] Mizuuchi T., Voitsenya V.S., Chechkin V.V. et al
1999 J. Nucl. Mater. 266-269 1139
[2] Chechkin V.V., Voitsenya V.S., Mizuuchi T. et al
2000 Nucl. Fusion 40 785
[3] Chechkin V.V., Grigor’eva L.I., Smirnova M.S. et al
2002 Nucl. Fusion 42 192
[4] Mizuuchi T., Ang W.L., Kobayashi T. et al 2002
Asymmetric divertor plasma distribution observed in
Heliotron J ECH discharge 15th International
Conference on Plasma Surface Interactions in
Controlled Fusion Devices Gifu, Program and Book
of Abstracts Paper P1-64 (Toki, Japan: NIFS).
[5] Gurevich А. V., Dimant Ya. S. 1990 Kinetic theory
of fast particle transport in tokamaks, in Reviews of
50
0 50 100 150 200 250 300 350
0
5
10
15
20
0
5
10
0 50 100 150 200 250 300 350
I
n /
,
m
A
/1
0
m
_ e
18
-3
P/ , kW/10 m
s
ne
_ 18 -3
A-A
TOP
BOTTOM
N = 4
N = 13
(a)
(b)
Plasma Physics, Vol. 16 (Kadomtsev, B.B., Ed.),
Consultants Bureau, New York, p.3
51
Institute of Plasma Physics, National Science Center “Kharkov Institute of Physics and Technology”, Akademicheskaya st. 1, 61108 Kharkov, Ukraine
In the divertor region:
- the total flow of diverted plasma increases (Fig. 5);
- a predominant rise of the diverted plasma flow in the ion toroidal drift direction, with the asymmetry index rising with power (Fig. 6).
References
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