introduction of hl-2m divertor design - iaea na€¦ · hl-2a cs and pf coil parameters of hl-2m...
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HL-2A
G.Y. Zheng1, X.R. Duan1, X.Q. Xu2, D.D. Ryutov2, L.J. Cai1, X.
Liu1, J.X. Li1, T.Y. Xia3, Y.Y Lian1, L. Xue1, Y.D. Pan1 and B. Li1
1Southwestern Institute of Physics, Chengdu, China
2Lawrence Livermore National Laboratory, Livermore, USA
3Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, China
Introduction of HL-2M divertor design
Vienna, 29 September – 2 October 2015
The 1st IAEA Technical Meeting on Divertor Concepts
HL-2A
Content
1. Configuration design of HL-2M
2. Properties of divertor configurations
3. Divertor target geometry and simulation
4. Engineering design and X-point control
5. Plan and summary
HL-2A
•R: 1.65 m
•a: 0.40 m
•Bt: 1.2~2.7 T
•Configuration:
Limiter, LSN divertor
• Ip: 150 ~ 480 kA
•ne: 1.0 ~ 6.0 x 1019 m-3
•Te: 1.5 ~ 5.0 keV
•Ti: 0.5 ~ 2.8 keV
Heating:
ECRH/ECCD: 5 MW
(6 X 68 GHz/0.5MW/1s, 2 X 140 GHz/1W/1s)
NBI (tangential): 3 MW
LHCD: 2 MW (4/3.7 GHz/500 kW/2 s)
Diagnostics: over 30, e.g. CXRS, MSE, ECEI…
Fuelling system (H2/D2): Gas puffing (LFS, HFS,
divertor), Pellet injection (LFS, HFS),
SMBI /CJI (LFS, HFS)
LFS: f =1~80 Hz, pulse duration > 0.5 ms
gas pressure < 3 MPa
HL-2A
HL-2A
Plasma current Ip = 2.5 (3) MA
Major radius R = 1.78 m
Minor radius a = 0.65 m
Aspect ratio R/a = 2.8
Elongation Κ = 1.8-2
Triangularity δ > 0.5
Toroidal field BT = 2.2 (3) T
Flux swing ΔΦ= 14Vs
Heating power 25 MW
Main parameters
HL-2M (new tokamak, under construction)
HL-2M tokamak
Mission: high performance, high beta, and high bootstrap
current plasma; advanced divertor (snowflake, tripod), PWI.
HL-2A
Test the engineering and physics issues
relevant to to fusion reactor, such as ITER
and CFETR.
Heat flux at target can be roughly compared,
(total heating power is 25MW, λq less than
2mm with Ip = 3MA).
HL-2M
Mitigation of heat flux at target to support
HL-2M high performance operation.
High performance plasma and advanced divertor
HL-2A
CS and PF coil parameters of HL-2M
R(mm) Z(mm) W(mm) H(mm)Ncoil
(Nr×Nz)
Max(kA)
PF1 912 185 50.4 352.4 28(2×14) 14.5
PF2 912 586 50.4 352.4 28(2×14) 14.5
PF3 912 987 50.4 352.4 28(2×14) 14.5
PF4 912 1388 50.4 352.4 28(2×14) 14.5
PF5 1092 1753 183 220 28(5×6) 38
PF6 1501 1790 257 146 27(7×4) 39.41
PF7 2500 1200 183 220 28(5×6) 39
PF8 2760 480 183 220 28(5×6) 35.29
CS 748 0 116.75 3442.3 96(2×48) 110
HL-2M
CS and PF coil parameters of HL-2M
All of PF Coil current can be reversed for HL-2M
HL-2A
Standard divertor to advanced divertor
PF4/L and PF6/L as divertor coils to generate two
separate X-points;
PF5/L adjusts position of the two X-points to
satisfy design requirements, such as snowflake
divertor configuration.Standard divertor
HL-2M
Snowflake Tripod
HL-2A
Ip(MA) R (m) a (m) Κ δ up δ down li βp
EFIT 1.2 1.71 0.56 1.698 0.265 0.735 1.17 0.645
CORSICA 1.2 1.71 0.55 1.694 0.255 0.745 1.17 0.64
EFIT CORSICA
Equilibrium benchmark by EFIT and CORSICA
HL-2A
Standard divertor Exact SF divertor SF divertor-plus SF divertor-
minus
Ip(MA) R (m) a (m) Κ δ up δ down li βp
2.0 1.78 0.62 1.73 0.3 0.74 1.20 0.60
Snowflake configurations of HL-2M
HL-2A
Exact-SF
When the plasma current reduces, the second X-point is fixed and first X
point is forced to moved up by take advantage of poloidal field of CS coil:
When plasma current is 0.9MA, the distance between the X-points will be
more than 50cm.
SF-minus Tripod Tripod
Snowflake divertor to Tripod dievrtor
HL-2A
Standard divertor
Weak Bp region of HL-2M SF divertor
Exact-SFStandard SF-plus SF-minus
D.D. Ryutov, et al., Contrib. Plasma Phys., 52, 539, 2012; PPCF, 54, 124050, 2012.
Fast convective heat transport around
weak Bp can increase power sharing
among the divertor legs and broaden
the heat flux profile at target.
HL-2A
Weak Bp region of HL-2M SF/Tripod divertor
When the distance between the two X-points
becomes large, configuration loses features of
snowflake divertor, becoming just two
separate X-points;
Tripod configuration has a long divertor leg
and three outgoing branches of the separatrix.
HL-2AThe local shear
The integrated magnetic shear
Magnetic shear and curvature analysis of SF
Same main parameters, R, a, Ip, k95, q95.
Same pressure and current profiles.
(Local magnetic shear)
Radius of curvature on outer mid-plane
HL-2A
The linear growth rate
Snowflake-minus improves P-B mode instability
The snowflake-minus has the closest X-point to the outer mid-plane
is able to affect the property of ballooning modes.
The second X-point improves the bad curvature in favor of the
suppression of P-B modes.
HL-2A
SF
SD
The TQ and the CQ phaseThe hot vertical displacement phase
Configuration evolution during VDE
Parameters Ip (MA) R0 (m) a (m) κ95 βp li δ95 Bt (T)
Value 1.00 1.71 0.55 1.65 0.60 1.06 0.25 2.20
HL-2A
30cm
The configurations (standard,
snowflake and tripod) of HL-2M can
be explored by optimizing the target
geometry;
High cooling ability to support the
high heat flux operation;
Flexible support structure, and well
protection for cooling pipe system;
Easy installation, maintenance and
update.
Divertor engineering design consideration
HL-2AStandard divertor Exact snowflake Snowflake minus
Target plate geometry of HL-2M
Divertor target geometry is expected to be compatible with the
configurations of HL-2M.
Ip=2MA Ip=2MA
HL-2A
Bp / Bt value around target of HL-2M divertor
γmin ≈ Bp/Bt sinα., if γmin too small,
the shadows and hot spots may
appear on the plate;
γmin is assumed to be 1/50 of a
radian (roughly 1 degree).
Standard divertor
Exact snowflake
Snowflake minus
HL-2A
Connection length
If λq=2mm of HL-2M, the plasma-wetted area:
more than 1.5m2 of SF and about 0.3m2 of SD;
P=12MW, 8MW/m2 of SF, 40MW/m2 of SD.
Standard divertor Snowflake minus
Mesh of SD and SF
0.000 0.005 0.010 0.015 0.020 0.025 0.030 0.035 0.0400.0
0.5
1.0
1.5
2.0
2.5
Rati
o o
f co
nn
ecti
on
len
gth
Distance from separatrix at outer middle plane (m)
Standard divertor
Snowflake divertor
Surface expansion
0.00 0.01 0.02 0.03 0.040
20
40
60
80
100
120
140
Su
rface e
xp
an
sio
n
Distance from separatrix at outer middle plane (m)
Standard divertor
Snowflake divertor
Ip=2MA Ip=2MA
HL-2A
Simulation boundary conditions of SD and SF
Cross field transport factor: D = 0.2m2/s, χe = χi = 0.5m2/s;
Power flows into SOL/Divertor regions: P = 12MW,
Pi=Pe=6MW;
The density is fixed about 4cm inside the separatrix, and the
upstream density ne,sep = 2.5*1019/m3;
The pumping gas speed S=50m3/s;
Carbon as impurity is included;
When Ip=2.0MA, the plasma density limit is about 1.5*1020/m3.
HL-2A 2MW/m2 of SF, and about 5.8/m2 of SD.
Heat flux distribution of SD and SF
The heat flux distribution at outer
target of standard divertor
The heat flux distribution at outer
target of snowflake minus
0.0 0.1 0.2 0.3 0.4 0.5 0.6
0
1x106
2x106
3x106
4x106
5x106
6x106
He
at
flu
x W
/m2
Distance from separatrix at outer target (m)
Standard divertor
Snowflake divertor
Heat flux profiles at outer target
HL-2A
Electron density at outer target
Electron density at outer target of SD and SF
0.0 0.1 0.2 0.3 0.4 0.5 0.6
0.0
2.0x1020
4.0x1020
6.0x1020
8.0x1020
1.0x1021
1.2x1021
1.4x1021
De
ns
ity
(/m
3)
Distance from separetirx at outer targte (m)
Standard divertor
Snowflake divertor
Standard divertor
Snowflake minus
HL-2A
Carbon ion density distribution of SD
C4+ C6+C5+
C3+C2+C1+
HL-2A
C3+C2+C1+
C4+ C6+C5+
Carbon ion density distribution of SF
HL-2A
Zeff distribution of SD and SF
0 20 40 60 80 1001.0
1.5
2.0
2.5
3.0
Zeff
From inner target along poloidal direction to ourter target
Standard divertor
Snowflake divertor
Inner target
Near X point
Outer mid-plane
Near X point
Outer target
Standard divertor
Snowflake minus
HL-2A
Peak heat flux at outer target of SF and SD
8 10 12 14 16 18
1x106
2x106
3x106
4x106
5x106
6x106
7x106
8x106
He
at
flu
x (
W/m
2)
Power flows into SOL/Divertor region (MW)
Standards divertor
Snowflake divertor
2.1x1019
2.4x1019
2.7x1019
3.0x1019
3.3x1019
2.0x106
4.0x106
6.0x106
8.0x106
1.0x107
1.2x107
Standard divertor
Snowflake divertor
He
at
flu
x
(W/m
2)
Electron density at outer mid-plane (m3)
The peak heat flux of SF is about 35% of SD (P=8-18MW);
ne,sep = 2.0*1019/m3,2.3MW/m2 of SF, 10.8MW/m2 of SF.
Peak heat flux at target with different
power flows into SOL/Divertor region
Peak heat flux at target with different
Electron density at outer mid-plane
P=12MW
HL-2A
SF and Tripod divertor configurations, Ip = 0.5MA
Snowflake minus Tripod 2Tripod 1
Ip = 0.5MA Ip = 0.5MA Ip = 0.5MA
HL-2A
D = 0.3m2/s, χe = χi = 1.0m2/s; P = 8MW, Pi = Pe = 4MW;
ne,sep = 1.4*1019/m3; Pumping speed is 50m3/s;
Carbon as impurity is included.
Mesh and boundary conditions of SD and SF
Snowflake minus TripodTripod
Ip = 0.5MA Ip = 0.5MA Ip = 0.5MA
HL-2A
0.00 0.01 0.02 0.03 0.04 0.05
10
20
30
40
50
60
70
Su
rfa
ce
ex
pa
ns
ion
Distance from separatrix at outer mid-plane (m)
Standard divertor
Snowflake minus (YX-point
= 120cm)
Tripod 1 (YX-point
= 110cm)
Tripod 2 (YX-point
= 100cm)
Connection length and surface expansion
Ratio of connection length of four
kinds divertor configurationSurface expansion of four kinds
divertor configuration
0.00 0.01 0.02 0.03 0.04 0.05
0.2
0.4
0.6
0.8
1.0
1.2
1.4
1.6
1.8
Rati
o o
f co
nn
ecti
on
len
gth
Distance from separatrix at outer mid-plane (m)
Standard divertor
Snowflake minus (YX-point
= 120cm)
Tripod (YX-point
= 110cm)
Tripod (YX-point
= 100cm)
HL-2A
Heat flux distribution of SF and Tripod
0.0 0.1 0.2 0.3 0.4 0.5 0.6
0
1x106
2x106
3x106
4x106
5x106
Heat
flu
x (
W/m
2)
Distance from separatrix at outer target (m)
Standard divertor
Snowflake minus (YX-point
= 120cm)
Tripod (YX-point
= 110cm)
Tripod (YX-point
= 100cm)Snowflake minus
Tripod 2
Tripod 1Standard divertor
HL-2A
Zeff distribution of different configurations
Snowflake minus Tripod 2Tripod 1Standard divertor
HL-2A
Carbon ion density distribution
C4+ C6+C5+
C4+ C6+C5+
Snowflake minus
Tripod 2 Tripod 2 Tripod 2
Snowflake minus Snowflake minus
HL-2A
-0.05 0.00 0.05 0.10 0.15 0.20 0.25
0.0
2.0x105
4.0x105
6.0x105
8.0x105
1.0x106
1.2x106
1.4x106
1.6x106
1.8x106
He
at
flu
x (W
/m2
)
Distance from the separatrix (m)
Ip=1.2MA
Ip=0.9MA
Ip=0.7MA
-0.05 0.00 0.05 0.10 0.15 0.20 0.25
0.0
2.0x105
4.0x105
6.0x105
8.0x105
1.0x106
1.2x106
1.4x106
1.6x106
1.8x106
He
at
flu
x (W
/m2)
Distance from the separatrix (m)
Ip=1.2MA
Ip=0.9MA
Ip=0.7MA
-0.05 0.00 0.05 0.10 0.15 0.20 0.25 0.30 0.35 0.40 0.45
0.0
2.0x105
4.0x105
6.0x105
8.0x105
1.0x106
1.2x106
1.4x106
1.6x106
1.8x106
He
at
flu
x (W
/m2
)
Distance from the separatrix (m)
Ip=1.2MA
Ip=0.9MA
Ip=0.7MA
-0.05 0.00 0.05 0.10 0.15 0.20 0.25 0.30 0.35 0.40 0.45
0.0
2.0x105
4.0x105
6.0x105
8.0x105
1.0x106
1.2x106
1.4x106
1.6x106
1.8x106
He
at
flu
x (W
/m2
)Distance from the separatrix (m)
Ip=1.2MA
Ip=0.9MA
Ip=0.7MA
Ip = 0.7MA
P =10MW
ne= 1.5X1019/m3
Heat flux at targets of DN tripod divertor
Limit the power flows into inner divertor region.
Handle most of heating power by outer divertor.
HL-2A
Vacuum VesselFirst wall Divertor
Divertor and first wall engineering design
First wall: Graphite;
Target plate: CFC.
HL-2A
Divertor engineering design and fabrication
Cassette divertor structure of HL-2M
CFC as the plasma
facing material brazed on
the copper alloy heat sink;
Cooling and baking
channels are drilled inside
the target copper plates to
feed cooling water;
Channels are connected
to pipes embedded inside
the support frame;
Design of diveror structure: 80 sections, cassette, individual
cooling, link structure for stress release
HL-2A
In-vessel and ex-vessel cooling circuits Feeding and collection pipes
Cooling design and analysis
Variation of highest CFC temperature with time
10MW/m2, 5s
HL-2A
Development of W coatings on graphite and CFC
HL-2A
Development of W coatings on graphite and CFC
HL-2A
P0
P1
P3
P2
X2
X1
exp exp( , , )C x y
Locally expand the Grad-Shafranov equation:
X-points Control methods
Find coefficients, Cexp, with the Br and Bz at points(P0-P3) from RTEFIT
Control X1, X2, ρ and θCreated the relationship between the PF coils
current and the X-point locations:
1( )T T
PFI A A A W B
1 1 2 2[ , , , , ]
iso
T
iso
GA
X P G
B x y x y
where,
exp exp
exp
1 1 r z
PF r PF z PF
C CB Bx x
I C B I B I
X, P , G
2
20r
r r r z
So
HL-2A
Controlling the distance between two X-points
文件
文件 snow2 装置 HL-2M 炮号 99996 时间 0
模式
迭代误差 4.6e-03 迭代次数 22 运行模式 平衡模式 收敛与否 已收敛/ 1.0e-03 / 50
位形
位形中心r 1.798 位形中心z -0.099 小半径 0.606 位形 下单零
上三角形变 0.326 下三角形变 0.784 截面积 1.906 体积 20.729
上拉长比 1.570 下拉长比 2.021 边界磁通 -0.283 磁轴磁通 0.246
电流
IPF1 -11.60 IPF2 -12.03 IPF3 -0.89 IPF4 4.53 IPF5 -7.82 IPF6 0.22 IPF7 -17.51 IPF8 -9.54
IPF9 -11.60 IPF10 -13.03 IPF11 -0.89 IPF12 14.53 IPF13 -18.72 IPF14 8.02 IPF15 -16.01 IPF16 -17.34
IP 2000.00 IE -39.56
1 1.5 2 2.5
-1.5
-1
-0.5
0
0.5
1
1.5
Control two X-points
文件文件 snow2 装置 HL-2M 炮号 99996 时间 0
模式
迭代误差7.4e-03 迭代次数 20 运行模式平衡模式 收敛与否已收敛/ 1.0e-03 / 50
位形
位形中心r 1.811 位形中心z -0.114 小半径 0.604 位形 下单零
上三角形变0.288 下三角形变0.790 截面积 1.826 体积 20.046
上拉长比 1.527 下拉长比 2.030 边界磁通 -0.267 磁轴磁通 0.273
电流IPF1 -12.21IPF2 -12.03IPF3 -0.54 IPF4 4.52 IPF5 -7.96 IPF6 -0.04 IPF7 -17.13IPF8 -9.89
IPF9 -9.43 IPF10 -18.95IPF11 6.09 IPF1215.70IPF13 -31.78IPF1419.09IPF15 -19.41IPF16 -16.06
IP 2000.00IE -39.56
0.8 1 1.2 1.4 1.6 1.8 2 2.2 2.4 2.6 2.8
-1.5
-1
-0.5
0
0.5
1
1.5
0 5 10 15 20-800
-600
-400
-200
0
200
400
sum
__delt__Ip
f(A
)
dIPF1U
dIPF2U
dIPF3U
dIPF4U
dIPF5U
dIPF6U
dIPF7U
dIPF8U
0 5 10 15 20-1.5
-1
-0.5
0
0.5
1
1.5x 10
4
sum
__delt__Ip
f(A
)
dIPF1L
dIPF2L
dIPF3L
dIPF4L
dIPF5L
dIPF6L
dIPF7L
dIPF8L
PF5
PF3
PF2
PF6
0 2 4 6 8 10 12 14 16 18 20-50
0
50
100
150
200
R-Z
(mm
)
The different of Xpoints' position from the target points
dRX1
dZX1
dRX2
dZX2
dRX = RX-target - RX-cur
dZX = ZX-target - ZX-cur
HL-2A
0 2 4 6 8 10 12 14 16 18 20-20
0
20
40
60
80
100
R-Z
(mm
)
The different of Xpoints' position from the target points
dRX1
dZX1
dRX2
dZX2
Controlling the second X-point
文件
文件 snow2 装置 HL-2M 炮号 99996 时间 0
模式
迭代误差 4.6e-03 迭代次数 22 运行模式 平衡模式 收敛与否 已收敛/ 1.0e-03 / 50
位形
位形中心r 1.798 位形中心z -0.099 小半径 0.606 位形 下单零
上三角形变 0.326 下三角形变 0.784 截面积 1.906 体积 20.729
上拉长比 1.570 下拉长比 2.021 边界磁通 -0.283 磁轴磁通 0.246
电流
IPF1 -11.60 IPF2 -12.03 IPF3 -0.89 IPF4 4.53 IPF5 -7.82 IPF6 0.22 IPF7 -17.51 IPF8 -9.54
IPF9 -11.60 IPF10 -13.03 IPF11 -0.89 IPF12 14.53 IPF13 -18.72 IPF14 8.02 IPF15 -16.01 IPF16 -17.34
IP 2000.00 IE -39.56
1 1.5 2 2.5
-1.5
-1
-0.5
0
0.5
1
1.5
dRX = RX-target - RX-cur
dZX = ZX-target - ZX-cur
0 5 10 15 20-400
-300
-200
-100
0
100
200
300
sum
__delt__Ip
f(A
)
dIPF1U
dIPF2U
dIPF3U
dIPF4U
dIPF5U
dIPF6U
dIPF7U
dIPF8U
0 5 10 15 20-8000
-6000
-4000
-2000
0
2000
4000
6000
8000
sum
__delt__Ip
f(A
)
dIPF1L
dIPF2L
dIPF3L
dIPF4L
dIPF5L
dIPF6L
dIPF7L
dIPF8L
PF5
PF3
PF2
PF6
Control the second X-points
HL-2A
Phase I: no feedback control, plasma vertical position grows exponentially
Phase II: feedback control of plasma vertical position start at the same time
k95 1.53 1.56 1.58
Growth rate 169 177 186
k95 1.55 1.58
Growth rate 162 208
I II
k95=1.58
I II
k95=1.58
SF SD
VDE control analysis of SF and SD divertor
HL-2A
Complicate configurations of HL-2M
More codes be involved in HL-2M divertor design and analysis,
such as SOLPS-ITER, EMC3, SOLEDGE and so on. The affect of
the second X-point will be investigated.
HL-2A
According to the lower divertor operation results, the upper
divertor will be designed and installed;
Based on the W coating technology developed at SWIP, the
first wall and target plate with W coating will be carried out
step by step;
The PWI researches based on HL-2M advanced divertor will
be studied, as well as the compatibility with the high
performance core plasma operation;
The particle control ability of HL-2M will be enhanced.
Possible divertor engineering update
HL-2A
Summary
Divertor configurations, properties analysis, target design,
divertor simulation, engineering design and configuration
control works are carried at SWIP for HL-2M divertor design.
Based on the design and analysis, standard and advanced
divertors will be are explored in HL-2M experimental research
project to study the divertor physics and mitigate heat flux for
high heating power operation.
Advanced divertor is an important mission of HL-2M, the
divertor physics, engineering design, code simulation and so on
are challenges for us now.
HL-2A
Thank you!