fishtail divertor heat load on divertor plant · 2017. 11. 29. · •input heating power~...
TRANSCRIPT
Fishtail divertor – Swing strike point for active control of
heat load on divertor plantX.D. Zhang1, Y Zhang1, J.P. Qian1, J.X. Zhen1, B. Li1, G.N. Luo1, Q. Yu2, S.J. Du1, L. Wang1, B.J. Xiao1, D.M. Yao1, Y.Y. Huang1
1Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, P.R.China2Max-planck Institute of Plasma Physics, D85748, Garching, Germany
A S I P P
*X.D. Zhang, et al, IAEA Second Technical Meeting on Divertor Concepts,13 – 16 November 2017, Suzhou China, P-3
Tel: 86-551-5591894 Fax: 86-551-5591310 E-mail: [email protected]
A new divertor concept, the Fishtail divertor (FTD), is proposed and investigated on
EAST.
FTD can quickly move the strike point along the radial and poloidal direction like
the swing of fishtail by additional alternating magnetic field.
The maximum moving distance of the strike point is active controlled by the
alternating field amplitude.
The wetted area of the heat flux is widened, so that the averaged heat load is reduced.
PF coils are needed and set behind divertor plates near the strike point, the
alternating magnetic field effect on the location of X points is very small .
Introduction
SN Divertor configuration
in Tokamak like fishtail
Long-pulse hybrid scenario in JT-60U
Long pulse H-mode operation with upper W divertor
• Input heating power~ 5MW,heat flux of ~3 MW/m2
on the divertor , temperature increase ~500℃
• Plasma is uncontrollable when the temperature on the
divertor plate is above 600℃
Periodic change of divertor configuration: USN-DN-
LSN.
• Moving strike points to Control heat load on target and
reduce the temperature of divertor for steady-state operation.
• Reduce impurities and material outgassing.
Development of divertor concepts
Some mew divertor concepts are developed to reduce the heat load unit area of divertor target.
These new concepts are all the static magnetic field
To broaden the distance between adjacent magnetic surfaces and increase heat flux channel widths in the
region from X point to target.
nonuniform distribution of the heat flux – the heat flux also need to be analyze and verified in broadening
magnetic field.
Strike point sweeping was firstly carried out on JET experimental
campaigns of 2006 year
Sweeping strategy was implemented within the Shape Controller
system, so the strike point sweeping is limited, only 4Hz.
The X point also produce larger displacement and changing of the gaps.
The Improvement effect is not significant. No cooling behind the plate
X-point
strike pointsFTD coil FTD coil
This divertor concept is like the strike point swing on JET,
but that is needed a special PF coil – FTD coil, which only
move the strike point.
FTD independent operation, does not affect the plasma
control system.
Strike point moving distance is controllable by controlling
the FTD coil current, so can active control of thermal
deposition area.
Because of the swing broadening, the heat flux deposition of
FTD is more uniform and is not to analyze the heat flux
distribution.
Reciprocating motion of the strike points like fishtail swing
Heat load has already become a crucial issuefor steady-state operation at high heating powerand requires a solution.
Divertor plate temperature gradually increased
due to long pulse operation
Impurities and outgassing from the divertor plate
affects the steady-state operation of tokamak.
Simulations of FTD Heat Load on Divertor
Possible advantages of FTD:
Good uniformity
Very small effect on the plasma
Good results for high and narrow heat flux
ELMy mitigation by means of fast swing
Neutron shielding of FTD coil
FTD can effectively reduce the heat load on the target and especially is more effectively for higher and
narrower heat flux.
May be used in the future reactor - must be controllable and safe:
1. Far away from the plasma, hidden behind the shield.
2. long leg divertor, special divertor chamber, combine with the
radiation divertor technology.
FTD Can Be Used in DEMO or CFETR ?
long leg
Neutron
shielding
FTD coil FTD coil
Target
Swing
Swing distance 10cm
Heat flux
Width1cm
10MW/m2
Heat flux
width 2cm
10MW/m2
C: no swing 1057 ˚C 1872 ˚C
C: 10 Hz 525 532
C: 20 Hz 520 525
C: 40Hz 516 520
Mo: no swing 1235 1994
Mo: 10 Hz 578 586
Mo: 20 Hz 572 578
Mo: 40Hz 567 570
W: no swing 1155 1878
W: 10 Hz 550 557
W: 20 Hz 544 550
W: 40Hz 540 544
Mo target
C target
FTD can make full use of the cooling capacity of the target plate and reduce the thermal stress of the material
Fishtail divertor – FTD and configuration
Design of FTD coil on EAST
1870
1090
Solution 1: 4 sections will be installed and brazing
Coil clamps
• TU1 conductor, OD30/ID15
• Ceramic sleeves ID33,OD46
Solution 2: 1 complete coil will be installed
• TU1 condutor+MgO layer +316L conduit• Shrinkage after assembly• Clamps are employed to hold the coil firmly
26m1086.529 S24 m10766.1 sA
1.74m1l
4109.9R H101.21 -5L
228.0|| Z
AC current operation
• Low frequency mode: 10-100Hz , 5kA
• High frequency mode: 3kHz, 4.2kA
Parameters estimation
Two solutions for the coil manufacture
and installation
Long-pulse H mode operation with input power of 20-30MWwill take a biger challenge to the EAST divertor
T. Eich,et al., NF 53(2013) 093031
High heat load on the divertor target plate is
one of the major problems to be solved for fusion
reactors
The recent results of multi-machines show that
the heat flux channel widths is extremely narrow in a
reactor and about 1/5 of the initial estimate value.
In DEMO the heat flux widths is more narrow than
in ITER.
On EAST, the heat load has already become a crucial issue for steady-state operation at high heating
power, so a special operation mode is required to reduce the target temperature
Heat Flux on Divertor Target in Tokamak Divertor in Steady State Operation
WITER
~350 MJ
W
PFC of ITER,
10MW/m2 for SS
20MW/m2 for 10s
EAST (2012) > 400s EAST (2016) H-mode > 60s
EAST (2017) H-mode > 100s
Divertor in long-pulse operation on EAST
As the heat flux increases, the target temperature increase is very small
if the striking point swing.
Heat deposition zone can be expanded by 100 times for ~mm heat flux.
p
p
F
Fs
I
d
d
Ikd
cmdkAI sF 10,5
Simulation of FTD heat load on EAST divertor
Heating flux 10MW/m2, spreading distance ~10cm.
Temperature on the divertor plate is reduced about 2~3
factor
No significant decrease when sweeping frequency is
above 10Hz
No swing Swing with 10Hz
EAST
ITER-like
Simulation of FTD heat load on ITER-like divetor
Heating flux 20MW/m2, width ~1 mm, and
spreading distance ~10cm
Temperature is reduced almost half by using FTD
sweeping frequency of 10Hz