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JT-60SA divertor research strategy and radiative scenario modelling
with improving SONIC integrated code
2nd IAEA Technical Meeting on Divertor Concepts, 13-16 November 2017, Suzhou, China
K. Hoshino1, T. Nakano1, M. Wischmeier 2, M. Sakamoto 3 and the JT-60SA team 1 National Institutes for Quantum and Radiological Science and Technology, Japan 2 Max-Planck-Institut fur Plasmaphysik, Germany 3 University of tsukuba, Japan
lv-11
JT-60SA HP:
http://www.jt60sa.org/b/index.htm
Support ITER using break-even-equivalent class high-temperature deuterium plasmas lasting for a duration (~100 s).
Supplement ITER toward DEMO with long sustainment (~100 s) of high pressure steady state plasmas necessary in DEMO.
JT-60SA (superconducting tokamak)
ITER (France)
DEMO Foster next
generation
Contribute to early realization of fusion energy by addressing key
physics and engineering issues for ITER and DEMO.
Foster next generation of scientists and technicians
playing leading roles in R&D of ITER and DEMO
demonstration of power generation
DT burning
JT-60SA (super advanced) project 2
the Satellite Tokamak Program in the JA-EU Broader Approach Activity and
the Japanese national programme
Highly Shaped Large Superconducting Tokamak
JT-60SA:
Large superconducting tokamak
High plasma current (max. IP=5.5 MA)
Long pulse (typically 100 s)
High heating power (41 MW × 100 s)
Highly shaped (S=q95Ip/(aBT) ~7, A~2.5)
Full-monoblock carbon DIV, first wall
(Metallic wall in later phase)
Non-circular superconducting tokamaks
3
Plasma current, IP (MA) 5.5
Toroidal magnetic field, BT (T) 2.25
Major radius, Rp (m) 2.96
Aspect ratio, A 2.5
Elongation, kx 1.95
Triangularity, dx 0.53
Safety factor, q95 3.0
Injection power, Pin (MW) 41
Normalized beta, bN 3.1
Bootstrap current ftacution, fBS 0.28
Full IP, 41 MW operation
Construction of JT-60SA is progressing smoothly by the EU
and JA Integrated Project Team towards the first plasma in
Sep. 2020.
4
Disassembly of JT-60U
Vacuum vessel & Thermal shield
Cryostat base
Lower poloidal field coil
Vacuum vessel
Toroidal field coil
Construction ~ First plasma
First plasma
2011 2012
Construction
Operation
Year 2021 2008 2009 2010 2013 2014 2015 2016 2017
Disassembly Assembly
Commissioning
Preparation
2018 2019 2020
Experiment
Integrated
Commissioning
Changeover to Full Metal Wall ~2030 (TBD)
Partially W
(or W-coated CFC)
divertor tiles. ITER
H / He Possibility of
W-coated full monoblock CFC divertor
+ full W-coated first wall
+ fully water-cooled ~2030
5
JT-60SA Research Phase
JT-60SA Research Plan 6
“JT-60SA Research Plan (SARP)” summarizes
“Research items and Strategy for JT-60SA”
to solve critical issues in ITER and DEMO.
Points of the JT-60SARP
Make a plan
Encourage collaborative studies on JT-60SA
Optimize hard ware: heating, fueling, pumping, diagnostics, etc.
Growing year by year toward fruitful experiments.
Chapter 2: Research Strategy
Chapter 3: Operation Regime Development
Chapter 4: MHD Stability and Control
Chapter 5: Transport and Confinement
Chapter 6: High Energy Particle Behavior
Chapter 7: Pedestal and Edge Physics
Chapter 8: Divertor, SOL and PWI
Chapter 9: Fusion Engineering
Chapter 10: Theoretical models and simulation codes
Ver. 3.3: Mar. 2016
365 colleagues
(13 countries, 42 inst.)
join activities led by
Technical Responsible
Officers (TROs) in the
research fields.
7
• 15 MW/m2x100 s for 3000 cycles
• 10 MW/m2x100 s for 10000 cycles
Target Plate
Divertor Cassette
Dome Plate
Cryopump
CFC mono-block
pumping speed of 0 -100m3/s by 8 steps
Heat & Particle Control with ITER-like-shaped Divertor
V-shaped corner
high neutral compression enhancement of detachment
Divertor to control heat & particle for the long-pulse, high-confinement and high-density operation
high radiative divertor plasma
Initial Research I
(1-2y)
Initial Research II
(2-3y) Integrated Research I
(2-3y)
H/He D D
Power: 23 MW 33 MW 37 MW
Divertor : CFC tile (10 MW/m2 x 5s ) C mono-block(15 MW/m2 x 100s)
Divertor research strategy (1/2)
Impurity seeding experiment ⇒ Multi-impurity simulation (C+Ne/Ar)
High power & radiation exp. ⇒ impurity-impurity collision
time-dependent SONIC + core transport model
Real time control of Ne/Ar seeding
H/D mixture exp. ⇒ integrated sim. with
SONIC and core transport model
simulation including radiation transport
Geometry effect red: experiment
blue: model development &
simulation study Neutral transport / compression
comparison with JT-60U, simulation
linkage with
code development
/ model validation
are progressed
from initial phase
8
Initial Research I
(1-2y)
Initial Research II
(2-3y) Integrated Research I
(2-3y)
He exhaust exp. ⇒ simulation including
elastic coll., HeH molecule,
meta-stable, radiation transport, etc.
multi-impurity sim. (He+C+Ne/Ar)
He exhaust exp. with Ne/Ar seeding
Full-W wall
experiment
Scenario development with full-W wall
multi-impurity sim. + core transport model
W transport (Monte-Carlo kinetic model)
PWI simulation (MC kinetic + BCA model)
red: experiment
blue: model development &
simulation study
Toward changeover to full metal wall,
code development & simulation study
will be progressed.
Divertor research strategy (1/2) 9
H/He D D
Power: 23 MW 33 MW 37 MW
Divertor : CFC tile (10 MW/m2 x 5s ) C mono-block(15 MW/m2 x 100s)
The SONIC simulation for prediction of the JT-60SA divertor plasma
10
integrated divertor code, SONIC H. Kawashima, Plasma Fus. Res. 2006, K.Shimizu NF2009
MC: Monte-Carlo
by execution of several models on the integrated-modeling
framework newly developed
Recently, the SONIC code has been extended to multi-impurity
simulation using MC kinetic model
Neutral
MC kinetic
Impurity(Ar)
MC kinetic
SONIC
Plasma
fluid
data exchange
A number of models
are attachable.
Impurity(Ne)
kinetic Impurity(W)
kinetic Impurity(C)
MC kinetic
on new integrated-modeling framework
Predictive studies for JT-60SA divertor plasma
JA: SONIC (H.Kawashima JNM2011 CPP2017, K.Hoshino CPP2014, etc.) EU: JINTRAC(M.Romaneli NF2017), COREDIV(R.Zagórski NF2016, K.Gałązka PPCF2017)
Prediction accuracy is improved by considering
the generation of a wall impurity and its transport
Previous SONIC
Present SONIC
Ar (MC kinetic)
0.17 Pam3/s
C (coronal model)
nC/ni = 0.01
Ar (MC kinetic) C (MC kineic)
Ychem = 3% 0.16 Pam3/s
Ar radiation
Ar radiation
C radiation
C radiation
Very different profile
Multi-impurities by MC kinetic model
including phys. & chem. sputtering
Only one impurity by MC
11
12
• Low SOL Density (ne,sep <1.7x1019 m-3)
from core plasma scenario nebar = 5.0x1019m-3 (ne
bar/nGW=0.85)
JT-60SA mission: steady-state (SS) and high-b (> 3.5) operation.
Steady-state high-b operation is challenging
for divertor power handling
Zeff=2 for intrinsic C is assumed
but no other impurities.
By using Pin=24MW,
a plasma with βN=3.9, HH=1.5
(Bt=1.7 T, Ip=2.3 MA) & nearly
full CD condition was obtained.
Example of scenario by 1.5D core transport simulation (N.Hayashi, IAEA FEC2016)
• High SOL density is preferable
for reduction of divertor heat load to desired level of < 10 MW/m2
To develop the divertor power handling scenario under the low SOL density condition,
multi-impurity SONIC simulation with Ar seeding is performed.
Radiative divertor scenario compatible with the SS high-b scenario is found.
13
D2 puff : 8.5 Pa m3 / s & Ar puff: 0.15 Pa m3 / s
Ar radiation
5.6 MW
C radiation
7.4 MW
SONIC simulation for parameter survey of gas puffing rate of D2 and Ar
mid-plane outer divertor
< 1.7 x 1019 m-3
< 10 MW/m2
characteristic profiles
for C and Ar.
the SONIC result
compatible with the
operation scenario
with Ar seeding
C generation consistent
with plasma and Ar
(phys. & chem. sputtering)
W/O Ar
W/ Ar
W/O Ar
W/ Ar
K.Hoshino, PET17
SONIC simulation for W-wall is progressing
W & Ar are treated by a coronal model
for Full-Ip(5.5MA), Full power(41MW) and High-density
( nW/ni=1e-5 )
• In W-wall case w/o Ar (red), qpk<10MW/m2 is difficult due to low Prad
• By increasing Γpuff and nAr /ni (blue), qpk<10MW/m2 can be achieved.
• Other seeding impurity
• Detailed analysis with
multi kinetic impurity model
H.Kawashima CPP2016
nAr/ni = 0%
0.01 %
0.1%
Power handling scenario for full W-wall was studied
Future work
14
Γpuff
15 Summary
• Construction of JT-60SA is progressing smoothly by the EU and JA
Integrated Project Team towards the first plasma in Sep. 2020.
• JT-60SA Research Plan (divetor/sol/pwi in chap.8) is evolving through
discussions between EU & JA.
• The divertor plasma performance for steady-state high-b scenario has
been analyzed by the SONIC code with kinetic impurity model.
The radiative divertor scenario for the heat load < 10MW/m2 under
SS high-b plasma condition (Pin=24MW, ne,sep<1.7x1019m-3) was obtained.
• Changeover to full metal wall is planed, and the SONIC simulation with a
coronal model for full W-wall has been performed.
The target heat load < 10MW/m2 was obtained by the Ar puff
(nAr/ni~0.001), under the condition of full Ip, full power and high density.
Research plan V.4 will be documented in Mar. 2018.
• The multi-impurity simulation using a MC kinetic impurity model for full
metal wall is in preparation.