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Ion temperature gradient turbulence simulations and plasma flux surface shape

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A generalization of the circular ŝ-α local magnetohydrodynamic (MHD) equilibrium model to finite aspect ratio (A), elongation (κ), and triangularity (δ) has been added to a gyrokinetic stability code and our gyrofluid nonlinear ballooning mode code for ion temperature gradient (ITG) turbulence. This allows systematic studies of stability and transport for shaped flux surfaces with the same minor midplane radius label (r), plasma gradients, q, ŝ, and α while varying A, κ, and δ. It is shown that the (linear, nonlinear, and sheared) E×B terms in the equation of motion are unchanged from a circle at radius r with an effective field Bunit = B0ρdρ/rdr, where χ = B0ρ2/2 is the toroidal flux, r is the flux surface label, and B0 is the magnetic axis field. This leads to a “natural gyroBohm diffusivity” χnatural, which at moderate q = 2 to 3 is weakly dependent on shape (κ) at fixed Bunit. Since Bunit/B0∝κ and 〈∣∇r∣2〉 ≈ (1+κ2)/(2κ2), the label independent χITER = χnatural/〈∣∇r∣2〉 at fixed B0 scales as 2/(1+κ2) with much weaker scaling at high-q and stronger at low-q where increased κ is stabilizing. The generalized critical E×B shear rate to be compared to the maximum linear growth rate is a flux surface quantity (r/q)d/dr(cq/rBunitdϕ0/dr) = (r/q)d(Ex0/BpR)/dr. © 1999 American Institute of Physics.
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Ion temperature gradient turbulence simulations and plasma flux surface
shape
R. E. Waltz and R. L. Miller
Citation: Phys. Plasmas 6, 4265 (1999); doi: 10.1063/1.873694
View online: http://dx.doi.org/10.1063/1.873694
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Ion temperature gradient turbulence simulations and plasma
flux surface shape
R. E. Waltza) and R. L. Millerb)
General Atomics, P.O. Box 85608, San Diego, California 92186-5608
Received 24 February 1999; accepted 29 July 1999
A generalization of the circular sˆ-
local magnetohydrodynamic MHDequilibrium model to finite
aspect ratio A, elongation
, and triangularity
has been added to a gyrokinetic stability code
and our gyrofluid nonlinear ballooning mode code for ion temperature gradient ITGturbulence.
This allows systematic studies of stability and transport for shaped flux surfaces with the same
minor midplane radius label r, plasma gradients, q,sˆ, and
while varying A,
, and
. It is shown
that the linear, nonlinear, and shearedEBterms in the equation of motion are unchanged from
a circle at radius rwith an effective field BunitB0
d
/rdr, where
B0
2/2 is the toroidal flux,
ris the flux surface label, and B0is the magnetic axis field. This leads to a ‘‘natural gyroBohm
diffusivity’’
natural, which at moderate q2 to 3 is weakly dependent on shape
at fixed Bunit .
Since Bunit /B0
and
r
2
(1
2)/(2
2), the label independent
ITER
natural /
r
2
at
fixed B0scales as 2/(1
2) with much weaker scaling at high-qand stronger at low-qwhere
increased
is stabilizing. The generalized critical EBshear rate to be compared to the maximum
linear growth rate is a flux surface quantity (r/q)d/dr(cq/rBunitd
0/dr)(r/q)d(Ex0/
BpR)/dr1999 American Institute of Physics. S1070-664X9901411-1
I. INTRODUCTION AND SUMMARY
The dependence of magnetohydrodynamic MHDsta-
bility limits on tokamak plasma shape is well known and
long studied both theoretically and experimentally. The de-
pendence of confinement on shape has been studied experi-
mentally, but hereafter theoretical micro-instability growth
rates, and particularly, diffusion loss rates have not been
given the full attention they deserve. A previous study by
Hua, Xu, and Fowler,1using a high-nlinear ballooning mode
code for ion temperature gradient ITGmodes, showed
growth rates in the plasma core decrease with elongation, but
are insensitive to triangularity. A key difficulty with previous
studies has been that high-nballooning instabilities micro-
instabilitiesare local and should only depend on local
plasma and flux surface shape parameters, whereas the stud-
ies varied the global equilibrium, making it unclear what
local parameters if anyremained fixed as the shape varied.
Furthermore, no comparison with the standard analytic infi-
nite aspect ratio circular s-
local equilibrium model2was
made.
The present paper uses a generalization of the s-
model
to a finite aspect ratio A, elongation
, and triangularity
local equilibrium model by Miller et al.3This allows sys-
tematic studies of growth rates versus local flux shapes with
the same minor midplane radius label r, plasma density and
temperature gradients, q,sˆdlnq/dlnr and
the MHD
pressure gradient parameterwhile varying A,
, and
.
Growth rates
can be conveniently normalized to cs/aunit ,
where csis the local ion sound speed and aunit is the unit of
length for measuring rand all gradient lengths. We will take
aunit as the flux surface label rat the last closed flux surface.
Since growth rates can be displayed as a spectrum in k
s,
where k
nq/rspecifies the toroidal mode number nand
scs/(eBunit /cMi) specifies the norm of the ion gyrora-
dius, growth rates refer only to n/Bunit and there is no sepa-
rate specification for n, and more importantly, the unit of
magnetic field Bunit ; thus Bunit is a free parameter in linear
theory.
While it may be sufficient in some cases such as the
core plasmato specify growth rates, or more accurately,
critical temperature gradients for marginal stability (
0),
more generally, the local heat diffusivity is needed. Apart
from the possible effects of diamagnetically dominated E
Bshear stabilization effects, the EBdiffusivity will
have a unit gyroBohm scaling DgB(cs/aunit)
s
2. The latter
is the natural norm for diffusion from a high-nnonlinear
ballooning mode representation.4Thus, diffusivity will scale
as 1/Bunit
2. This paper shows that if we choose Bunit as
B0
d
/rdr, where
is defined through the toroidal flux
B0
2/2 where B0is the magnetic field on the magnetic
axis, then all linear, nonlinear, and sheared EBphysics
appear to be identical to that in a circular plasma of minor
radius rwith magnetic field Bunit . Thus using ras a flux
surface label, we obtain a heat diffusion loss rate
1/Vr
/
rVrn0
ˆnaturalDgBdT0/dr,1
where VdV/dr with Vthe flux surface volume. Also in
Eq. 1n0and T0are the local density and temperature,
respectively, and
ˆnatural is the heat diffusivity normalized to
the unit gyroBohm diffusivity DgB . Using a nonlinear bal-
looning mode gyrofluid code for ITG turbulence4reformu-
lated to shaped geometry with the Miller local equilibrium,
aElectronic mail: Waltz@gav.gat.com
bPresent address: Archimedes Technology Group, Inc., 5405 Oberlin Drive,
San Diego, California 92121.
PHYSICS OF PLASMAS VOLUME 6, NUMBER 11 NOVEMBER 1999
42651070-664X/99/6(11)/4265/7/$15.00 © 1999 American Institute of Physics
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we find for moderate q2–3and well above marginal sta-
bility and in the absence of EBshear, that
ˆnatural is weakly
dependent on shape despite the fact that the maximum ITG
growth rates can decrease significantly with increasing shap-
ing, or specifically, with increasing elongation.
It was found previously4–6 in circular geometry that
when the EBshear rate
Ebecomes comparable to the
maximum growth rate
max , the ITG turbulence vanishes
i.e.,
Ecrit
E
max ;
E1. In shaped geometry we find
that the appropriate EBshear rate is a flux surface variable
reminiscent of the circular formulation
Er/qd/drcq/rBunitd
0/drr/qdEx0/BpR/dr.
2
The factor (r/q) can be significantly smaller in elongated
plasmas than the corresponding factor (BpR/B) in the com-
monly used real geometry Hahm–Burrell formula7as mea-
sured on the outboard side.Bpis the poloidal field and
0(r) is the electrostatic potential and Ex0the radial electric
field. Since (BpR/B) is not a flux function, neither is the
Hahm–Burrell rate. We hasten to add that the Hahm
Burrell formula was derived in the context of a general two-
point renormalization theory and not in the context of the
simulations with a ballooning mode formalism; thus there is
actually no quantitative basis for comparing it with the maxi-
mum growth rate.In the limited study of real geometry in
this paper, we find
E0.5 is a better fit than the circular fit
of 1.0.
This simple mnemonic formulation has an immediate
consequence: To convert a circular sˆ-
transport model
e.g., Ref. 8to real geometry, use the circular model and the
circular Eqs. 1and 2, but replace the toroidal magnetic
field by an effective field Bunit(r)B0Sh(r) where Sh(r)
d
/rdr is the shape factor, and ris the flux surface label.
Well the threshold for instability and ignoring EBshear
effects, and to the extent that the
ˆnatural is approximately
constant, gyroBohm diffusive confinement time would scale
as (ShB0aunit)2at fixed midplane minor radius. Shcan ac-
quire rather large values e.g., 2–10 from the center to the
edge even for
1.6. For concentric elliptical shapes
Sh(r)
. It is possible to take a profile of Miller’s local
equilibria from experimental discharges and rescale only the
profile in
. Rescaling a typical discharge to a nearly circular
plasma (
1), we still find the profile of Shcan still vary
from 1.3 to 3 and we also find that Sh
.
To understand how this simple recipe compares with
previous modeling recipes, we need to define diffusivity
more carefully. In terms of Eq. 1, the International Toka-
mak Experimental Reactor ITERModeling Group,9defines
a standard diffusivity
r
2
ITER
ˆnatural DgB . Substitut-
ing this in Eq. 1, we see that
ITER has the very useful
feature of being independent of flux surface label; that is, we
could replace the rlabel by
,
,or⌿共the poloidal flux.We
will continue to use ras a flux surface label, and for illus-
tration, consider concentric ellipses, in which case
r
2
(1
2)/(2
2). If
ˆnatural is in fact exactly constant at
fixed Bunit and gyroBohm-like, then
ITER at fixed B0,r,
T0,qwould scale as 2/(1
2). Under the same conditions
and on the basis of empirical low L-mode confinement time
scaling
1/2 at fixed current and power, Kinsey et al.10 and
Bateman et al.,11 posited that
ITER would exhibit a much
stronger 1/
4scaling. The models of Refs. 8 and 12 give
ITER
r
/
r
2
, which is a weakly decreasing function
of
. As we show in some detail,
ˆnatural is constant only at
moderate q23, well away from the critical gradient.
From a survey of our limited ITG simulations, ranging over
1to2,
ITER scales as 2/(1
2)or1/
1.3 at q2–3.At
low q1.5 where increasing
can stabilize the ITG modes,
it scales more strongly, 1/
2.1. At high q4, it scales more
weakly as
0.03. Clearly the dependence on elongation is not
separable from the other dependencies.
In Sec. II we show in detail how the EBterms in any
equation of motion retain their circular form with an effec-
tive field Bunit , and formulate the components of the balloon-
ing mode representation for Miller’s local equilibrium. Some
details are given in Appendix A. In Sec. III, some illustra-
tions of stability versus the shape variables
,
, and A
from a full dynamics linear gyrokinetic code are given. We
also show how the code recovers the MHD beta limit. Sec-
tion IV shows the result of our ITG gyrofluid simulations
with varying elongation and triangularity at numerous qval-
ues and temperature gradients, and in comparison to the sˆ-
local equilibrium. Finally we reexamine the rotational shear
stabilization criterion.
II. FORMULATION
To summarize the local equilibrium of Miller et al.3for
finite elongation and triangularity, we specify the shape of a
flux surface by the major radius Rand height Zas a function
of the position poloidal angle
.
RR0rcos
arcsin
sin
,3
Z
rsin
.4
The magnetic-field B
xⵜ⌿f
has poloidal and to-
roidal components Bp
r/R
r
and Btf/R, respec-
tively, where is the poloidal flux and
B0
2/2 is the
toroidal flux per 2
.qd
/d, is the average safety factor,
and
r
1
sin2
arcsin
sin
兴关1arcsin
cos
2
2cos2
1/2/
cosarcsin
sin
rR0cos
s
s
cos
1s
arcsin
cos
sin
sin
arcsin
sin
.5
Note that
r
1 in an infinite aspect ratio circle. In addi-
tion to q,sˆ(r/q)dq/dr, and the MHD pressure gradient
variable
q2(
rV/2
2)(V/2
2R0)1/24
␲⳵
rP/(rBunit)2
q2R0d
/dr for a circle, we need to specify the aspect
ratio AR0/r, the local Shafranov shift rate
rR0, the elon-
gation
, the triangularity
, and the gradients, s
(r/
)
r
,s
r/(1
2)1/2
r
. The latter are essen-
tially degenerate variables which may be approximated as
s
(
0)/
, where
0is the on axis value, and s
/(1
2)1/2 when not provided by the profile of elonga-
tion and triangularity. It follows that:
4266 Phys. Plasmas, Vol. 6, No. 11, November 1999 R. E. Waltz and R. L. Miller
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BpBunitr/Rq
r
6
and
BtBunitr/R/
d
/2
dl/d
/R
r
,7
where lis the poloidal arc length and B2Bp
2Bt
2.
Following Bishop et al.,13 the ballooning mode represen-
tation follows entirely from the shape see Eqs. 3and 4兲兴
and the magnetic-field solutions to MHD equilibrium Eqs.
5and 6. This requires that the field perturbations be writ-
ten in eikonal form FFn,kx0(
)exp(inSikx0
r
x). The
eikonal, S, and poloidal flux, , are expanded in a normal
distance xfrom the flux surfaces: S
S0(
)xS1(
) and
0x1x22.
is the toroidal angle, nis the tor-
oidal mode number, which we will specify through k
nq/r. The radial Fourier transform wave number kx0is
often written in terms of the ballooning angle label
0:kx0
⫽⫺k
sˆ
0. We can establish a map between the poloidal
arc length laround the flux surface and
, which can be
considered the extended poloidal angle starting at the outer
midplane. At each location
, the magnetic-field direction b
ˆ
and the cross field directions yˆ and xˆ in and out of the sur-
face, are oriented with respect to a locally orthogonal grid
system (
ˆ,lˆ,xˆ). Then
ˆ/R,llˆ, and xxˆ.S
and xdetermine the rapid variation of the perturbations
across the magnetic field, such that b
ˆS0 and b
ˆx
0. The slow variation along the field are determined by the
variations in Fn,kx0(
). The parallel field derivative on a
perturbation is given by
b
ˆ
Bp/Bd
/dl
1/R0q
,8
where here and below refers to the infinite aspect ratio
circular limit. The rapid cross field derivatives are given by
y⫽⫺in yˆSikyin/RB/Bpik
rB/RBpqik
,
9
which follows from S0(
), and
x⫽⫺inxˆSikx0
r
ikxiky关关共kx/ky兴兴ikx0
r
ik
sˆ
sin
sˆ
0,10
which follows from S1(
) with xˆSRBpS1(q)/RBp.We
define (rB/RBpq)关关qˆ 兴兴(
)1. The explicit forms for the
eikonal components S0and S1taken from Ref. 13 and the
important function 关关kx/ky兴兴(
) are given in Appendix A.
Considering the cross-field derivatives we can illustrate
how the EBmotion has a circular form with an effective
field Bunit . Apart from this, all formulas here are identical to
the circular analogues of Refs. 4–6. In physical units the
relevant terms in the continuity equation for density pertur-
bations are given by
n
˜
/
t/n0
˜
En0/n0
˜
En
˜
/n0
E0n
˜
/n0¯.
11
From
˜
Ec(
˜
b
ˆ)/Band
0Ec(
0b
ˆ)/Bit is
straightforward to show that
˜
En0/n0i
¯
*e
/Te
icTe/eBunitk
dlnn0/dre
/Te,
12
which clearly identifies the diamagnetic drift frequency
¯
*
as a flux function. The nonlinear term is
˜
En
˜
/n0kc/Bunitk
1kx0
2k
2kx0
1
1n2/n0,
13
where we have made use of the result
r
关关qˆ 兴兴/B
1/Bunit , and the cancellation of the 关关kx/ky兴兴(
) part of kx
in the cross product of k(1)b
ˆk(2). The sum over wave
number, k, satisfies the usual conditions; namely k
(2)k
k
(1) and kx0
(2)kx0kx0
(1) . The Doppler shift and EB
shear terms are given by
E0n
˜
/n0⫽⫺incq/rBunitdln
0/dr
d/dr关共cq/rBunitd
0/dr
r
xn
˜
i
En
˜
Ek
n
˜
/
kx0,14
where we made a Taylor expansion of the Doppler shift as a
flux function. We used dr
r
xand the Fourier identity
r
x⫽⫺i
/
kx0to define the EBshear rate
Eas in
Eq. 2.
¯
Eis the Doppler shift frequency, which clearly
must be a flux function as it refers to a single mode. The
shear rate is also a flux function. As we have defined it, it is
smaller by the factor (r/q)/(BprR/B)关关qˆ 兴兴(
) than the
commonly used Hahm–Burrell formula.7On the outboard
side 关关qˆ 兴兴(
) could be O(1/3) for a
2 plasma. The dif-
fusivity is defined from the transport continuity equation
n0/
tx
˜
Exn
˜
source, 15
where
x
˜
Exn
˜
⫽⫺1/Vr
/
rVr
r
2
Dnatural /
r
2
dn0/dr,16
with
Dnatural
c/Bunitik
˜
n
˜
/n0
/dlnn0/dr.17
As we noted in the Introduction, the combination
Dnatural /
r
2
DITER is independent of the flux surface
label. V(r)
d
(dS/d
)/
r
, where the differential sur-
face area is (dS/d
)(dl/d
)2
R(
). In deriving Eq.
17we took the normal flux at the flux surface to be
˜
Exn
˜
⫽⫺ik
(c/Bunit)
˜
n
˜
/
r
, again making use of the identity
r
关关qˆ 兴兴/B1/Bunit . Also the surface average of any func-
tion Fis defined to be
F
d
F(dS/d
)/
r
/
d
(dS/d
)/
r
. The later surface averaging is a very
weak function of
; for perfectly nested ellipses (s
0,s
0,
rR00), the surface average becomes
F
d
FR(
)/
d
R(
), which can be ignored i.e., replaced
with a simple
averageat high aspect ratio. Thus apart from
the special surface average Dnatural , is virtually identical to
the circular formula. The conversion to dimensionless units
proceeds as in Ref. 5 with the unit of macro-length, aunit rat
the last closed flux surface,
scs/(eBunit /cMi) the unit of
micro-length e.g., k
sk
,DgB(cs/aunit)
s
2the unit of
4267Phys. Plasmas, Vol. 6, No. 11, November 1999 Ion temperature gradient turbulence simulations and...
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diffusion, cs/aunit the unit for rates, and perturbations nor-
malized to
s/aunit e.g., (e
/Te)/(
s/aunit)
.
To obtain gyrofluid closures or gyrokinetic equations
reminiscent of the circular limit, we need only specify fur-
ther the arguments of the Bessel functions (zk
i) for the
gyroradius averages and the curvature frequency
D
k
i2Ti/Te1/2k
s
关关B
ˆ兴兴1/2关关qˆ 兴兴/关关B
ˆ兴兴
1共关关kx/ky兴兴kx0
r
/关关qˆ 兴兴2
1/2,18
DTi/Tek
scs/aunit2aunit /R0关关qˆ兴兴/关关B
ˆ兴兴
1关关B
ˆ兴兴/2共关关cos兴兴共关关kx/ky兴兴
kx0
r
/关关qˆ 兴兴关关sin兴兴
1关关B
ˆ兴兴
关关cosp兴兴
,19
where
(v/vth)2,
关关B
ˆ兴兴(v/vth)2with
and gyro-
average constants of motion and the Maxwellian aver-
age of
(1关关B
ˆ兴兴/2)1 and
(1关关B
ˆ兴兴)1
2. Further
关关B
ˆ兴兴(
)B/Bunit1, 关关cos兴兴(
)cos(
) and 关关sin兴兴
(
)sin(
) refer to the normal and geodesic curvature
components, and 关关cosp兴兴(
)0 refers to the finite beta ef-
fect of grad-Bminus curvature drift. These functions of
are
discussed in Appendix A.
III. SOME EXAMPLES OF GYROKINETIC LINEAR
STABILITY IN REAL GEOMETRY
The initial value electromagnetic gyrokinetic code, first
developed by Kotschenreuthers’,14 was modified using the
formulation of Sec. II. In addition, following the gyrokinetic
formulation of Antonsen and Lane,15 parallel magnetic per-
turbations (B
˜
) were added to the electrostatic and magnetic
vector potential perturbations (
˜
,A
˜
). This code was inde-
pendently modified for real geometry and B
˜
by Dorland and
Kotschenreuter16 and several code checks were made. Table
I gives a sample deuterium benchmark for the equilibrium
given in Ref. 3 A3.17, q3.03,
1.66,
0.416, s
0.7, s
1.37, sˆ2.85 Ref. 3 sˆMHD2Vq/qV2.47,
rR0⫽⫺0.345,
1.22 and r/a0.83, a/LT3, a/Ln
1, Ti/Te1, nei0, k
s0.3. In the one fluid MHD
limit (k
s0) there is a cancellation of terms such that B
˜
can be dropped as long as Bdrift is replaced with curvature
drift, i.e. zero pterms in 关关cos兴兴(
) and 关关cosp兴兴(
) terms
of Eqs. A9and A11. Remarkably, this MHD recipe holds
rather well even at finite k
s, as shown by the fourth line of
Table I.16 Figure 1 shows recovery of the ideal critical
at
2.4.
An important feature of the Miller’s local equilibrium is
the ability to scan in parameter space away from the sˆ-
model. Figure 2 shows a scan away from the standard circu-
lar point r/a1
2,R/a3i.e., A6,q2, sˆ1, a/LT
3, a/Ln1, Ti/Te1,
0(
0), Vei0. In Fig. 2a
we can see the effects of finite aspect ratio, and in Fig. 2b
we see the general improvement with elongation. Figure 2c
shows that reverse triangularity gives an improvement, likely
because of the drift reversal on the trapped electron drive.
This is reminiscent of the ‘‘comet’’ shape effect.17 Figure
2dshows that there can be lower growth rates in going to
low aspect ratio, but only in the absence of trapped electrons.
Aspect ratio scans at fixed
were made in Ref. 18. However,
the main benefit of low aspect ratio Ais seen by scans at
fixed
and fixed shift (
R0) with
1/A. As shown in Fig.
3, growth rates do not increase, yet MHD stability can be
realized at much higher
i.e.,
crit independent of Aand q.
Another important feature of Miller local equilibria is that
they can be reconstructed from a stored plasma profile data
FIG. 1. Growth rate
scan through the MHD critical point
2.4 of Ref.
3 Miller’s sample local equilibrium A3.17, q3.03,
1.66,
0.416, s
0.7, s
1.37, sˆ 2.85,
rR00.345,
1.22, and r/a
0.83, a/LT3, a/Ln1, Ti/Te1,
ei0, k
s0.3.
FIG. 2. Growth rate scan in wave number aelongation b, triangularity
c, and aspect ratio dabout a standard point r/a1/2, R/a3i.e., A
6,q2, sˆ 1, a/LT3, a/Ln1, Ti/Te1,
0(
0), vei0.
TABLE I. Bench point test at a reference local equilibrium.
A
B
,
Ref. 16
,
Off Off electrostatic 0.29, 0.09兲共0.30, 0.0927
On Off 0.31, 0.16兲共0.327, 0.166
On On 0.40, 0.20兲共0.426, 0.21
On Off B
0.39, 0.214
4268 Phys. Plasmas, Vol. 6, No. 11, November 1999 R. E. Waltz and R. L. Miller
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base having R(
), r(
),
(
),
(
), as well as Ti,e(
) and
ni,e(
)e.g., the ITER transport profile data base in Ref. 9.
Figure 4 shows the stability profile reconstruction of the
DIII-D19 negative central shear Shot No. 84736,20 compar-
ing real geometry to the electrostatic and the finite-
sˆ-
model. Here we can see that there can be substantial finite-
stabilization in the core plasma, yet the sˆ-
model is known
to have a critical-
substantially below that possible with
shaped geometry.
From these examples of linear growth rates versus shape
parameters, we hesitate to make any general or quantitative
inferences about the benefits of shape. As we show in Sec. II
with nonlinear studies of turbulent transport for the ITG
modes with adiabatic electrons, the actual diffusivity well
above the critical temperature gradient does not follow linear
growth rates in a simple way. Documentation of the ITG
critical gradient with shape may be more useful than a docu-
mentation of growth rates.
IV. EXAMPLES OF NONLINEAR ITG MODE
SIMULATIONS IN REAL GEOMETRY
The code with a four-moment gyrofluid closure for adia-
batic electron ITG mode turbulence used in Refs. 4–6 was
reprogrammed with the formulation of Sec. II. Starting from
the standard case, well away from the critical gradient r/a
1
2,R/a3(A6), q2, sˆ1, a/LT3, a/Ln1, Ti/Te
1,
0(
0), Vei0, we move to finite elongation and
triangularity with s
(r/
)
r
(
1)/
,s
/(1
2)1/2. The key results are shown in Table II in dimen-
sionless units.
natural is in gyroBohm units with Bunit fixed.
Surprisingly, the
natural does not reflect the decrease in
max with shape and is apparently offset by the increase in
the mixing length 1/kx
max . For example, if we take kx
max to
be the spectral width in kx0for growth, and
mix
0/kx
2
net
max /(
max
2
max
2) with
0the damping rate of the n
0 modes at kx0k
max and
net
max
E
E0 here,
a formula used in Ref. 8, then
mix is 0.24, 0.19, and 0.17
for
1, 1.6, and 2. Unfortunately, we have not found an
expression for the mixing length that captures the depen-
dence on shape in a universal way.We also find that the
diffusion fluxballoons much more to the outside as elon-
gation is increased. From these limited cases, it appears that
norm
natural is not a strong function of shape. Thus the benefit of
shape in this case comes from the increase in the square of
the effective field (Bunit /B0)2
2. Thus confinement time at
fixed minor radius and B0would exhibit
2scaling well
away from a critical gradient. The last column of Table II
shows
ITER2/(1
2)1/
1.3 at fixed B0. This is not as
strong as 1/
4suggested by Kinsey et al.10 and Bateman
et al.,11 but stronger than the 1/
0posited by the transport
models of Refs. 8 and 12.
We hasten to add, however, that the quantitative depen-
dence on shape or more specifically elongationis not likely
separable from other parameters. For example, in Table III
we show that the dependence on
is much stronger at low q
(
ITER1/
2.1), where the increasing
drives closer to sta-
bility e.g., q1at
2 is stable, and much weaker
(
ITER
0.03) at high-q.
Previous work using the sˆ-
model4–6 showed that tur-
bulence vanishes when the shear rate satisfies
E
E
max
with
Enear 1.0 to within 20%–30%. In Sec. II, we showed
FIG. 3. Growth rate scans in aspect ratio at fixed
and
R0⫽⫺0.1,
2, s
0.5,
0 at various
from the standard point of Fig. 2.
FIG. 4. Growth rate normalized to cs(0)/aversus a normalized
using
local equilibria from a profile data base for DIII-D Shot No. 84 736 see
Ref. 19.
TABLE II. ITG diffusivity at increasing elongation and triangularity.
max kx
max
natural 1/
r
2
(B0/Bunit)2
ITER
sˆ
0.082 0.417 2.1 1 1 2.1
1 0 0.123 0.286 2.72 1 1 2.72
1.6 0 0.085 0.210 2.47 1.82 0.39 1.72
2.0 0 0.059 0.144 2.78 2.01 0.25 1.46
2.0 0.4 0.057 0.148 3.18 2.00 0.25 1.58
TABLE III. ITG diffusivity at increasing elongation for various q.
q
␬␥
max kx
max
natural
Bunit fixed Scaling of
natural
ITER
B0fixed
1.5 1 0.11 0.241 2.26 2.26
1.5 2 0.034 0.117 0.98
1.2 0.516
2.0 1 0.123 0.286 2.72 2.72
2.0 2 0.059 0.144 2.78
01.46
3.0 1 0.15 0.346 4.80 4.80
3.0 2 0.10 0.206 5.04
0.07 2.72
4.0 1 0.16 0.434 5.72 5.72
4.0 2 0.10 0.210 11.18
0.96 5.87
4269Phys. Plasmas, Vol. 6, No. 11, November 1999 Ion temperature gradient turbulence simulations and...
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how to properly generalize the shear rate to a flux function
Eq. 2兲兴. In Table IV, we show some examples about the
standard case for real geometry. From Table IV, we conclude
that
Earound 0.5 is more appropriate in real geometry
even at
1. It seems to take less rotational shear to sta-
bilize in real geometry; this may be due to the fact that the
extent of the unstable spectrum region
0, or the mode
width
is a smaller fraction of 2
for the finite aspect ratio
as compared to the sˆ-
model. Thus the mode spends less
time in its rotation through the outboard side see Ref. 6 for
discussion of the Floquet mode rotation picture. Recall that
Eas we have defined it is 关关q兴兴(0) times the commonly
used Hahm–Burrell shear rate at
0. 关关q兴兴(0) can easily
cancel the
E0.5 if one compares the Hahm–Burrell rate
to
max .
ACKNOWLEDGMENTS
This is work is supported by the U.S. Department of
Energy under Grant No. DE-FG03-95ER54309 and addition-
ally by the Grand Challenge Numerical Tokamak Turbulence
Project. We wish to acknowledge many useful discussions
with Dr. W. Dorland at the University of Maryland.
APPENDIX A: BALLOONING MODE LOCAL
EQUILIBRIUM FORMULATION
Field perturbations can be represented F
Fn,kx0(
)exp(inSikx0
r
x) with the eikonal Sex-
panded in a normal distance xfrom the flux surfaces as S
S0(
)xS1(
). Similarly, the poloidal flux is given
by 0x1x22. Following Ref. 13:
S0
⫽⫺f
0
d
dl/d
/R0
2Bp
2,A1
S1
RBpf
0
d
dl/d
/R3Bp
2
2 sinu/R2/Rcf/fRBp
4
Rp/Bpff/RBp
A2
1
RBp,A3
2
1/2
sinuR/RcBp4
R2pff
,A4
where dl2dR2dZ2gives the poloidal arc length with
dR/dlcos(u), dZ/dl⫽⫺sin(u), and du/dl⫽⫺f/Rc
df/dx, and pdp/d
. Explicitly,
kyn/RBp/BBp/RS0f/RBp
n/RB/Bp,A5
or kyk
关关qˆ 兴兴(
), defining 关关qˆ 兴兴(
)(rB/RBpq). In ad-
dition, we defined kxky关关kx/ky兴兴kx0
r
where
关关kx/ky兴兴共
⫽⫺RBp2/BS1
/RBp.A6
Decomposing
S1
/RBpD0
Dp
pDff
ff
and using q(f/2
)
d
(dl/d
)/R2Bp, it can be shown,
after much tedious algebra, that 2
q⫽⫺D0(2
)
Dp(2
)pDff(2
)ff, so that
S1
/RBpDff2
1
D0
Dff2
D02
Dff
Dp
Dff2
Dp2
Dff
p2
Dffq
.A7
Using qsˆ(RBp/
r
)(q/r) and pdp/dr(RBp/
r
)
Eq. A7gives 关关kx/ky兴兴 explicitly.
The curvature (
b
ˆb
ˆ) and grad-B(
B/B) drift fre-
quency is given by
¯
Dikyyˆkxxˆ2cTi/eBb
ˆ
1关关B兴兴
B/B␧␭关关B兴兴/2
,A8
This can be decomposed as in Eq. 19with
关关cos兴兴共
R0
xB2/2B2
R0Bp/B2Bp/Rc4
Rp
f2sinu/B2R3,A9
关关sin兴兴共
R0f/RBdl/d
B2/2B2,A10
关关cosp兴兴共
R04
pRBp/B2,A11
where we used
xB2/2B24
pRBp/B2xˆ
f2/R2B2
lB2/2B2lˆfBp/RB2
lB2/2B2
ˆ
A12
and
B/B
xB2/2B2xˆ
lB2/2B2lˆ.A13
To force Bdrift to equal curvature drift set the pterms in
Eq. A9and A11to zero.
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a/LT
␬␥
max
Ecrit
3 1 0.123 0.07
3 2 0.059 0.035
4 1 0.22 0.09
4 2 0.13 0.08
4270 Phys. Plasmas, Vol. 6, No. 11, November 1999 R. E. Waltz and R. L. Miller
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4271Phys. Plasmas, Vol. 6, No. 11, November 1999 Ion temperature gradient turbulence simulations and...
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A physically comprehensive and theoretically based transport model tuned to three-dimensional (3-D) ballooning mode gyrokinetic instabilities and gyrofluid nonlinear turbulence simulations is formulated with global and local magnetic shear stabilization and E×B rotational shear stabilization. Taking no fit coefficients from experiment, the model is tested against a large transport profile database with good agreement. This model is capable of describing enhanced core confinement transport barriers in negative central shear discharges based on rotational shear stabilization. The model is used to make ignition projections from relative gyroradius scaling discharges.
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Numerical simulations of ion temperature gradient (ITG) mode transport with gyrofluid flux tube codes first lead to the rule that the turbulence is quenched when the critical E×B rotational shear rate γE−crit exceeds the maximum of ballooning mode growth rates γ0 without E×B shear [Waltz, Kerbel, and Milovich, Phys. Plasmas 1, 2229 (1994)]. The present work revisits the flux tube simulations reformulated in terms of Floquet ballooning modes which convect in the ballooning mode angle. This new formulation avoids linearly unstable “box modes” from discretizing in the ballooning angle and illustrates the true nonlinear nature of the stabilization in toroidal geometry. The linear eigenmodes can be linearly stable at small E×B shear rates, yet Floquet mode convective amplification allows turbulence to persist unless the critical shear rate is exceeded. The flux tube simulations and the γE−crit ≈ γ0 quench rule are valid only at vanishing relative gyroradius. Modifications and limits of validity on the quench rule are suggested from analyzing the finite relative gyroradius “ballooning-Schrödinger equation” [R. L. Dewar, Plasma Phys. Controlled Fusion 39, 437 (1997)], which treats general “profile shear” (x variation in γ0) and “profile curvature” (x2 profile variation).
Article
Kinetic equations for low frequency, short perpendicular wavelength, electromagnetic perturbations in an inhomogeneous, magnetically confined plasma are developed. The analysis makes use of the recently developed high toroidal mode number expansion to reduce the lowest‐order system of equations to a set of ordinary (along the field line) integro‐differential equations. Included in these equations are the effects of finite Larmor radius, magnetic shear, trapped particles, and nonuniform magnetic curvature drifts. Perturbed fields are represented by a scalar potential and two components of the vector potential. Thus, the effects of the compressional component of the perturbed magnetic field are retained and the equations are valid for arbitrary values of the plasma pressure. The extension of the high toroidal mode number expansion to nonaxisymmetric configurations is discussed.
Article
The work of Xu and Rosenbluth [Phys. Fluids B 3, 627 (1991)] on ion-temperature-gradient modes in toroidal geometry is extended to noncircular cross sections to examine the scaling with the elongation κ. The growth rate, wave numbers, and stability thresholds are calculated for a flat density profile characteristic of H-mode operation, and a mixing-length estimate of the ion thermal diffusivity χi is calculated. It is found that in the plasma core, growth rates decrease as the central elongation κ increases, due to finite-Larmor-radius effects. The calculated χi is approximately of the form χi=DTi3/2[(LTi)c−LTi] where D and (LTi)c depend on Τ=(Te/Ti) and geometry, and LTi=&Verbar;Ti/∇Ti&Verbar;. Preliminary evidence indicates fair agreement with experimental data near the plasma edge, where LTi&Lt; (LTi)c, but the fit is poorer in the core where LTi∼(LTi)c and the theoretical χi is very sensitive to the accuracy in calculating (LTi)c.
Article
One of the scientific success stories of fusion research over the past decade is the development of the EÃB shear stabilization model to explain the formation of transport barriers in magnetic confinement devices. This model was originally developed to explain the transport barrier formed at the plasma edge in tokamaks after the L (low) to H (high) transition. This concept has the universality needed to explain the edge transport barriers seen in limiter and divertor tokamaks, stellarators, and mirror machines. More recently, this model has been applied to explain the further confinement improvement from H (high) mode to VH (very high) mode seen in some tokamaks, where the edge transport barrier becomes wider. Most recently, this paradigm has been applied to the core transport barriers formed in plasmas with negative or low magnetic shear in the plasma core. These examples of confinement improvement are of considerable physical interest; it is not often that a system self-organizes to a higher energy state with reduced turbulence and transport when an additional source of free energy is applied to it. The transport decrease that is associated with EÃB velocity shear effects also has significant practical consequences for fusion research. The fundamental physics involved in transport reduction is the effect of EÃB shear on the growth, radial extent, and phase correlation of turbulent eddies in the plasma. The same fundamental transport reduction process can be operational in various portions of the plasma because there are a number of ways to change the radial electric field E{sub r}. An important theme in this area is the synergistic effect of EÃB velocity shear and magnetic shear. Although the EÃB velocity shear appears to have an effect on broader classes of microturbulence, magnetic shear can mitigate some potentially harmful effects of EÃB velocity shear and facilitate turbulence stabilization. (Abstract Truncated)
Article
A procedure which reconciles long parallel wavelength, characteristic of plasma instabilities, with periodicity in a sheared toroidal magnetic field is described. Applied to the problem of high-n ballooning modes in tokamaks, it makes possible a full minimization of the potential energy functional deltaW and shows that previous calculations overestimated stability.
Article
Predictions are made for the performance of the International Thermonuclear Experimental Reactor (ITER) [R. Aymar, V. Chuyanov, M. Huguet, R. Parker, and Y. Shimomura, in Proceedings of the Sixteenth International Atomic Energy Agency Fusion Energy Conference, Montréal, Canada 1996 (International Atomic Energy Agency, Vienna, 1997), Paper IAEA-CN-64/01-1] design using the Multi-Mode model in the time-dependent one- and one-half-dimensional (1-1/2-D) BALDUR [C. E. Singer et al., Comput. Phys. Commun. 49, 275 (1988)] transport code. This model predicts the temperature and density profiles observed in present-day tokamak experiments more closely on the average than other models currently available. Simulations using the Multi-Mode transport model, with its inherent gyro-Bohm scaling, indicate that ITER will ignite, even with edge temperatures as low as 0.25 keV (L-mode, or low-confinement mode, boundary conditions) or with volume averaged density as low as 0.775×1020 m−3 (just below the Greenwald density limit, when Tedge=0.75 keV). The ignition is found to be thermally stable, and the fusion power production is easily controlled by varying plasma density, impurity content, or edge temperatures. The nonequilibrium impurity radiation model used in these simulations predicts that a significant fraction of the fusion power is radiated when conditions are close to marginal ignition. © 1998 American Institute of Physics.
Article
A tokamak equilibrium model, local to a flux surface, is introduced which is completely described in terms of nine parameters including aspect ratio, elongation, triangularity, and safety factor. By allowing controlled variation of each of these nine parameters, the model is particularly suitable for localized stability studies such as those carried out using the ballooning mode representation of the gyrokinetic equations. © 1998 American Institute of Physics.
Article
The suppression of turbulence by the E×B flow shear and parallel flow shear is studied in an arbitrary shape finite aspect ratio tokamak plasma using the two point nonlinear analysis previously utilized in a high aspect ratio tokamak plasma [Phys. Plasmas 1, 2940 (1994)]. The result shows that only the E×B flow shear is responsible for the suppression of flute‐like fluctuations. This suppression occurs regardless of the plasma rotation direction and is, therefore, relevant for the very high (VH) mode plasma core as well as for the high (H) mode plasma edge. Experimentally observed in–out asymmetry of fluctuation reduction behavior can be addressed in the context of flux expansion and magnetic field pitch variation on a given flux surface. The adverse effect of neutral particles on confinement improvement is also discussed in the context of the charge exchange induced parallel momentum damping. © 1995 American Institute of Physics.
Article
A fixed combination of theory-based transport models, called the Multi-Mode Model, is used in the BALDUR [C. E. Singer et al., Comput. Phys. Commun. 49, 275 (1988)] transport simulation code to predict the temperature and density profiles in tokamaks. The choice of the Multi-Mode Model has been guided by the philosophy of using the best transport theories available for the various modes of turbulence that dominate in different parts of the plasma. The Multi-Mode model has been found to provide a better match to temperature and density profiles than any of the other theory-based models currently available. A description and partial derivation of the Multi-Mode Model is presented, together with three new examples of simulations of the Tokamak Fusion Test Reactor (TFTR) [K. M. McGuire et al., Phys. Plasmas 2, 2176 (1995)]. The first simulation shows the strong effect of recycling on the ion temperature profile in TFTR supershot simulations. The second simulation explores the effect of a plasma current ramp—where the plasma energy content changes slowly on the energy confinement time scale. The third simulation shows that the Multi-Mode Model reproduces the experimentally measured profiles when tritium is used as the hydrogenic isotope in L-mode (low confinement mode) plasmas. © 1998 American Institute of Physics.