Diamagnetic flux study

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Transcript Diamagnetic flux study

Diamagnetic Flux, Li and Stored Energy discrepancies on MAST
Discrepancies have been found to exist on MAST between TRANSP,
EFIT and experimental data for the diamagnetic flux, li and stored
energy. This also seems to be the case for other tokomaks around the
world. In this study, various aspects are analysed which seem to
affect these profiles.
Are there differences between ohmic, co injection and
counter injection shot discrepancies?
Will the choice of data analysis via TRANSP affect the
discrepancies?
Is the experimental data correct?
Are the calculations in TRANSP and EFIT correct?
Ohmic, Co Inj and Ctr Inj Shots
Diamagnetic Flux
Ohmic shots have the best agreement between TRANSP, ttr_dflux, and EFIT,
efm_diamag_flux(c), the two sets of data lying to within +/-10% of each other, Fig 1a. Co
and ctr injection do not have such a good agreement with the co inj data lying to within +/30% of each other, Fig 1b, and ctr injection shots to within +/-40%, Fig1c.
For ttr_dflux Vs the experimental, amd_dia flux, Fig 2, the ohmic data, Fig 2a show that
ttr_dflux is greater and the data lie within 20% of each other. For co inj, ttr_dflux is also
greater to within 20%. A third result is produced for the ctr injection shots, Fig 2c, but here,
amd_dia flux is greater by 30%, however since there are not enough ctr shots for which
amd_dia flux exists, this is inconclusive.
For amd_dia flux Vs efm_diamag_flux(c), Fig 3, efm_diamg_flux(c) is greater for each
type of shot, by 20% for Ohmic, 20% for Co inj and 10% for ctr inj.
Stored Energy
TRANSP is consistently higher than EFIT by up to 40%, Fig 4.
Li
TRANSP is consistently higher than EFIT by up to 90%, Fig 5.
FIGURE 1: TRANSP Vs EFIT DIAMAGNETIC FLUX
A) OHMIC - +/- 10% to 0.2s
B) CO INJ- +/-30% to 0.2s
C) CTR INJ - +/-40% to 0.2s
FIGURE 2: TRANSP Diamagnetic Flux Vs amd_dia flux
a) OHMIC +/-20%
b) CO INJ +/-30%
c) CTR INJ +/-40%
FIGURE 3: amd_dia flux Vs efm_diamag_flux(c)
a) OHMIC +/-20% to 0.2s
b) CO INJ +/-20% to 0.2s
c) CTR INJ +/-10% to 0.2s
FIGURE 4: TRANSP Vs EFIT Stored Energy
a) OHMIC +/-40%
b) CO INJ +/-40%
c) CTR INJ +/-40%
FIGURE 5: TRANSP Vs EFIT LI
a) OHMIC +/-90%
b) CO INJ +/-90%
C) CTR INJ +/-90%
The Effect of Rotation
It is interesting to note how much closer the ttr_dflux and efm_diamag_flux(c) is for
ohmic shots, Fig 1a. Co and ctr shots have a toroidally rotating plasma; the
tangentially injected beams causing the plasma to rotate toroidally. Ohmic shots do
not rotate. Does rotation affect the diamagnetic flux? What about li and stored
energy?
Fig 6a shows ctr shot 8302 with rotation on, Fig 6b with rotation switched off. The
effect is to decrease the stored energy by about 10% since there is no longer any
rotational energy, and to increase the diamagnetic flux by about 20%. The
diamagnetic flux comes closer to EFIT and is slightly larger than amd_dia flux. Fig
6c shows a close up of the lis; li hardly changes.
Fig 7a shows co inj shot 7092 with rotation on, Fig 7b with rotation off. Again the
stored energy decreases by about 15% when the rotation is turned off, and the
absolute value of the diamagnetic flux increases by about 10%. Fig 7c shows that li
hardly changes.
Ttr_dflux seems to change most for ctr shots when rotation is switched off.
FIGURE6: Ctr Inj shot with and without Rotation
a) Ctr inj run 08302N03 - rot on b) Ctr inj run 08302N04 - rot off c) Li’s Compared for 08302N03/N04
FIGURE 7: Co inj Shot with and without Rotation
c) Li’s for 07092C02/C01
a) Co inj run 07092C02 - rot on
b) Co inj 07092C01 - rot off
The Effect of the Equilibrium Solver
The effect of the equlibrium solver cannot be ignored. Fig 8a shows the correlation between
the magnetic axis calculated by TRANSP and the corresponding diamagnetic flux, for run
08493N06, where there were problems with the solver, ESC. There are 3 possible solvers that
can be used in TRANSP for STs:
 ESC
= The Equilibrium and Stability Code (ESC) is a fast, up-down
asymmetric MHD toroidal equilibrium code written by L. E. Zakharov (PPPL)
solving the Grad-Shafranov equation in flux coordinates. The best option.
 RZsolver
= Solves the Grad-Shafranov equation in (R,Z) coordinates.
 VMEC6
= Variational Moments Equilibrium Code: 2-d code suitable for
modelling tokamak geometries of arbitrary moment and adapted to TRANSP.
Figs 8b, c and d show shots 8414, 8563, and 8564 analysed with these different solvers,
Fig8b 8414: ESC(red), RZsolver(green), VMEC6(blue)
 RZsolver badly overestimates the absolute value after about 0.2s
 ESC and VMEC6 agree quite well with EFIT until about 0.1s after which they
underestimate the diamagnetic flux
 amd_dia flux was not available
Fig 8c 8563: ESC(old(pink) and updated(green), VMEC6(blue)
 the three underestimate efm_diamag_flux(c) and amd_dia flux, until 0.16s
after which they overestimate amd_dia flux and underestimate
efm_diamag_flux(c).
Fig 8d 8564: ESC (old (yellow) and updated (green)), Rzsolver(blue), VMEC6(pink)
 The old ESC and VMEC6 again underestimate amd_dia flux and
efm_diamag_flux(c) until 0.14s after which they approach efm_diamag_flux(c)
 RZsolver agrees well with amd_dia flux until 0.1s after which it deviates
towards efm_diamag_flux(c), crossing it at 0.155s and then becoming even
larger
VMEC6 and the old ESC underestimate both and then cross amd_dia flux at
0.13s deviating towards efm_diamag_flux(c)
 The new ESC swings above and below amd_dia flux, crossing it at 0.17s and
then following the other solver data.
A difference is seen with the solvers, especially with RZsolver, but the quality and
accuracy of input data is vital. Figs 8c and 8d show that for the analyses carried out with
data of known Ti, the solvers are much closer in their answers. Generally, the ESC solver
is then used in the TRANSP analysis and upon a failure to converge, automatically
switches to RZsolver.
FIGURE 8: Comparison of Equilibrium Solvers
a) Diamagnetic flux and
Magnetic Axis for
08493N06
b) Shot 8414
c) Shot 8563
d) Shot 8564
Density and Fast Ion Energy Content Effect
There appears to be a density effect which has an effect on the li profile, pointed out by M.
Valovic. High density and low fast ion energy content at the TS time point seem to result in
better agreement between ttr_li and efm_li. For example,
Fig 9a shot 6953, run 06953X31, has 7% fast ion energy content and TRANSP li/
EFIT li = 0.99.
Fig 9b shows shot 8246, run 08246C02, where the agreement between the two
sets of li data is still good with a fast ion energy content of 16% and TRANSP li/
EFIT li = 1.034.
Fig 9c shows shot 8493, run 08493N08 which has a fast ion energy fraction of
35%, and TRANSP li/ EFIT li = 1.47. The shots are quasi stationary H mode
shots.
A more in depth analysis is given, Fig 10a, where TRANSP li/EFIT li at the TS point for
selected quasi stationary H mode co inj shots is plotted.
For TRANSP li/EFIT li to within 10% there are:
43% of shots with fast ion energy content below 10%
6% of shots with fast ion energy content between 10 and 20%
11% with f.i. content of 20 to 30%
none in the 30% and over range.
FIGURE 9: Fast Ion Energy Content Effect
a) Low Fast Ion Energy -06953X31 b) Medium Fast Ion Energy 08246C02
c) High Fast Ion Energy - 08493N08
Interestingly, for the f.i. group of 10 to 20%, 75% lie above the 30% limit verifying that
TRANSP is higher than EFIT for li, and also that efm_li does not vary as much as ttr_li
for this group.
The selection of ctr inj shots is smaller and seem to have less of a spread in results, Fig
10b. Again
43% of shots with f.i. content below 10% are within 10%., compared to
25% of those with f.i. content between 10 and 20% and
50% of those between 20 and 30%.
All of the shots with f.i. content above 30% gave results above 30%.
Fig 10c compares ttr_li and efm_li for seven shots. The lower three, 6762, 6953 and 8246
have the closest agreement and have fast ion energies of 9, 7 and 16% respectively,
whereas the upper four, 8414, 8416, 8493 and 8498 have 18, 17, 34 and 32% respectively,
and the agreement is not so good.
FIGURE 10: Fast Ion energy Content - Li
a) Co inj lis at TS
b) Ctr inj lis at TS
C) Lis for different FI Content
Fig 11 shows the same idea for the diamagnetic flux.
For the ohmic shots:
Fig 11a, 77% of all shots lie to within 10%, there is no f.i. content.
For the co injection shots, Fig 11b:
100% of shots with f.i. content below 10% lie to within 20%, and
57% to within 10% of each other.
For the 10 to 20% range, 35% lie within 10%,
47% to within 20% and 100% to within 30%.
The spread is not so large as for the li data.
Significantly, for the ctr inj shots, Fig 11c, most of all the f.i. content ranges lie in the
EFIT half, showing that efm_diamg_flux(c) is generally greater than ttr_dflux.
FIGURE 11: Fast Ion Energy Content - Diamagnetic Flux
a) OHMIC - +/-10%(no f.i)
b) Co INJ +/-10%
c) CTR INJ +/-10%
Fig 11 (cont) More Ohmic Data
d) Ohmic shots using New ESC - best taken
e) High Density Ohmic Shot-08995R02
Variation with H Factor
Do the results correlate to the Hh factor in any way?
Hh = tau_te_3/ tau_te(ipby2)_3 from tau00**.**.
Figs 12a and b show Hh Vs ttr_li/efm_li and Hh Vs ttr_dflux/efm_diamag_flux(c). There are
a lack of Hh values available for the data used and so the data pool is not as large as desired.
ttr_li/efm_li: Initially it looks like the ctr inj data is closer to 1 but the difference in the mean
X values is not large. The difference in mean Y values (Hh) is also not big, but Hh does
seem to be slightly larger for the ctr inj shots than for the co inj shots.
ttr_dflux/efm_diamag_flux(c): There is a much large difference in the mean X values and
the ctr inj shots can definitely be said to have efm_diamag_flux(c) > ttr_dflux, wheras the
opposite is true for the co inj shots. The Hh values are as above with the ctr inj shots having
larger Hh values.
HH Vs li(t)/li(e)
Figure 12a
2.5
2
Mean Y Co Inj
Co Inj
Ctr Inj
1.5
HH
Mean X Co Inj
Mean Y Co Inj
1
Series6
Mean Y Ctr Inj
Mean X Ctr Inj
0.5
0
0
0.5
1
1.5
2
li(t)/li(e)
HH Vs Dflux(t)/Dflux(e)
Figure 12b
2.5
2
Co inj
Ctr inj
1.5
HH
Mean X Ctr Inj
Mean X Co Inj
1
Mean Y Ctr Inj
Mean Y Co Inj
0.5
0
0
0.5
1
Dflux(t)/Dflux(e)
1.5
2
Varying the Q Profile used in TRANSP
The choice of q profile as used in TRANSP is important. Figs 13a and 13b show
ttr_dflux for runs 6953 and 7051 compared with efm_diamag_flux(c) and amd_dia flux
using different choices of q in the TRANSP analyses.
WORST agreement: smoothed EFIT q profile is used all the way through
the run without alteration, 6953(rust) and 7051(red)
NEXT WORST: 6953 only, initialising q with EFIT and then evolving q
with the PFDE, poloidal field diffusion equation, (green)
MODERATE: The other traces have EFIT q changing to the PFDE at
progressively later times, the later the better the agreement
BEST: using EFIT q all the way through apart from near the edge, ie; from
r/a=0.75 where it is modified, forcing consistency with the plasma current
data, (black). Fig 12b shows the same effect for 7051 (black).
By allowing TRANSP to modify the edge region of the q profile, a better agreement is
obtained.
Figs 13c and 13d show ttr_li against efm_li for the same sequence of runs as 13a and
13b. Again it can be seen that the best results are achieved for 06953X31 and
07051X98, (black).
FIGURE 13: Varying the Q Profile
EFIT q
throughout
b) Diamagnetic
Flux - 7051
a) Diamagnetic
Flux - 6953
c) Li - 6953
EFIT q
throughout
EFIT q
throughout
d) Li - 7051
EFIT q
throughout
JET Results
JET have observed errors in stored energy, diamagnetic flux and li also. Irina
Voitsekovic et al from JET have pointed out that the measured diamagnetic flux, DIFM,
and that calculated by EFIT, DIFC, are in good agreement for high density and medium
density shots, but DIFC deviates away from DIFM for low density shots. Fig 14a
shows shots
 61138, high density
 61079, medium density
 and 61132, low density
to TRANSP
: DIFC, DIFM agree, with TRANSP larger
: DIFC, DIFM agree, with TRANSP larger
: DIFC, DIFM not in agreement, DIFC closer
Fig 14b shows the same comparison for the lis. The differences are approximately 34,
34, and 24% with respect to TRANSP, so they all disagree quite substantially.
Therefore, it can be said that li does not follow the same trend as the diamagnetic flux.
However, more data is needed to finalise this.
FIGURE 14: Density Comparison of JET Data
a) JET Diamagnetic Flux Comparison
b) JET Li Comparison
Figure15: Effect of Argon Seeding (JET data)
Li
Transp
Transp
Diamagnetic Flux
a) 61371 - with Ar, 59351 - without Ar
b) Various Shots with Ar Seeding
Experimental Error
Amd_dia flux
The main source of error in the AMD_DIA FLUX signal is due to pick-up from the TF and
to a lesser extent the Solenoid field; the quoted error of +/-10% includes this. Recently, for
shots 10850 onwards, the best signals ever have been recorded. There has been a flat, noise-free
TF. This could be due to the fact that JET is not operational at the moment. RM is working to
improve matters.
Calculations in TRANSP and EFIT
Diamagnetic Flux
TRANSP: ESC solves the Grad-Shafranov equation in flux coordinates,  and .
RZsolver (used if no ESC convergence) solves it in (r,z) coordinates and is less likely to have
problems with a sharp sepratrix/ or diffuculty to correctly locate the magnetic axis than an
inverse solver such as ESC. ttr_dflux is calculated in
$CODESYSDIR/source/magcor/mgpout.for.
DO 40 J=LCP1, LEP1
JM1 = J-1
ZTF = XI(J,1)**2 * TFLUX (actual flux enclosed)
DFLUX = DFLUX + [(ZTF – ZTPF) * (1.0 –FBZ(JM1,2))/FBZ(JM1,2)]
ZTPF = ZTF
CONTINUE
Where TFLUX is the toroidal flux enclosed in the plasma from the eq solver routine
FBZ is the actual/external toroidal B field at the Zn/bdry (para/diamagnetism)
XI**2 = (PHI/PHILIM) is the relative toroidal flux label
LCP1 - INDEX TO OUTER BDY OF INNERMOST ZONE
LEP1 - INDEX TO PLASMA OUTER BDY
DFLUX is calculated by summing the toroidal flux over all zones and correcting by the factor (1FBZ)/FBZ .
NB: DFLUX is taken to be TRFLX * (1-FBZ)/FBZ. Is this ok?
TRFLX *(1-FBZ)/FBZ =  TFLUX * XI(JB1,1)2 *(1-FBZ)/FBZ
=  Btor(int) * XI(JB1,1)2 *(1-Btor(int)/Btor(ext))/Btor(int)/Btor(ext))
DFLUX =  (Btor(ext) – Btor(int)) *dArea
EFIT: solves the Grad-Shafranov in cylindrical RB.
EFM_DIAMAG_FLUX(C) is calculated using:
cdflux(iges) = cdflux() + (fnow-fbdry)/rgrid(I) *ww(kk)*darea
Where iges is a time point
fnow is RB at I
fbdry is RB is at boundary
ww(kk) is the weighting function at grid element kk, 0 outside plasma and 1 inside plasma
aarea is the area of the grid
rgrid is the position on the grid at I
Both ways are valid methods of calculating the diamagnetic flux.
Inductance
TRANSP: LI02 = 0.5*(total poloidal field energy)/(total plasma vol*local poloidal field energy
density/bdy)
EFIT:
EFM_LI = (B-p )2 dv / (<B-p >2  dv)
Where B-p is the poloidal magnetic field and B-p = 0  Iplasma /  dl
2*LI02 = EFM_LI
What are the Main Effects?
Diamagnetic Flux and Energy:
rotation,
density,
fast ion energy content,
choice of q profile in analysis,
accuracy of eq solver
Li:
fast ion energy content,
choice of q profile in analysis
accuracy of eq solver
Future:
More counter injection shots are definitely needed to get better statistics and a better feel for what
is going on. More high quality co inj shots in the quasi stationary H mode region again to improve
statistics. The
Any ideas?