transient em analysis of iter plasma -facing components
TRANSCRIPT
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Transient EM Analysis of ITER Plasma-facing ComponentsTimothy Burke, Thomas Holschuh
SAND2010-7328C
Sandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy’s National Nuclear Security Administration under contract DE-AC04-94AL85000.
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The Fusion Reaction•The peak DT reactivity is about 200 keV but a plasma temperature of about 20 keV (~100 MK) has a sufficient reaction rate•The reaction products are a 3.5 MeV alpha and a 14 MeV neutron•Deuterium is found in all water•Tritium is bred from lithium using fusion neutrons
Deuterium-Tritium Fusion Reaction
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Stars are confined by gravity.Terrestrial plasmas are
confined by either magnetic fields (many configurations) or inertially (inward momentum confines the plasma long enough for reactions to take place)The most common
magnetic scheme is the tokamak (bottom figure).
Plasma Confinement
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ITER
Largest tokomak device to be built
“The way” Prove the feasibility of fusion
technology, not produce power
First plasma to ignite in 2018 Collaboration of 7 National
Entities• United States, Russian
Federation, China, South Korea, Japan, European Union, India
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Central Solenoid
Outer Inter-coil Structure
Toroidal Field Coil
Poloidal Field Coil
Machine Gravity Support
Blanket Module
Vacuum Vessel
Cryostat
Port Plug
(IC Heating)
Divertor
Torus Cryopumping
ITER – The Device
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Total fusion power 500 MW
Additional heating power 50 MW
Q - fusion power/ additional heating power ≥ 10
Average 14MeV neutron wall loading ≥ 0.5 MW/m2
Plasma inductive burn time 300-500 s *
Plasma major radius (R) 6.2 m
Plasma minor radius (a) 2.0 m
Plasma current (Ip) 15 MA
Toroidal field at 6.2 m radius (BT) 5.3 T
Characteristics of ITER
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ITER - Blanket
Covers the interior of the vacuum vessel and magnets Modular - 440 individual segments, 1x1.5 m Thermal shielding, Nuclear Shielding weighing up to 4.6 tons
Courtesy of J. Kotulski
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First Wall and Shield
Blanket comprised of thin PFC First Wall and thicker Shield Block
First Wall serves as heat sink
Shield Block serves as neutron shield
Shield Block
First Wall
Slits in shield block to mitigate currents
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Pivot Point
First Wall and Shield - Continued
Courtesy of J. Kotulski
Slits in shield block to mitigate eddy currents
First wall comprised of “fingers” to mitigate currents
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Plasma Disruptions
Normal Plasma Plasma at end of Disruption, t = 50 ms
Dots represent plasma shape
Outline of First Wall
•Plasma dissipates in milliseconds
•Numerous causes
•Loss of Temperature
•Loss of Control
•Change in plasma current or magnetic fields causes plasma to move, eventually hitting the walls of the vessel
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Plasma Disruptions
•Rapid loss of current in plasma induces current in other structures
•Induced current in a magnetic field creates JxB forces and torques on objects
•Extreme current magnitudes mean extreme forces are possible 0.0E+00
5.0E+06
1.0E+07
1.5E+07
2.0E+07
0 0.02 0.04 0.06
Plas
ma
Cur
rent
(Am
ps)
Time (Seconds)
Plasma Current During Disruption
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Electromagnetic Analysis of Current Induced in ITER Blanket Modules
Tim Burke
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Blanket Module – Vacuum Vessel Interface
Different configurationsCenter/off center Hydraulic ConnectorDifferent Mount shorting scenariosDifferent impedances/conductivityDifferent Strip countsDifferent Strip positions
All of these have the potential to carry current to and from the vacuum vessel
Goal is to minimize current path through vacuum vessel as well as current magnitude
Mounts
Conducting Strips
Hydraulic Connector
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The Model
•Simple, imperfect model in design and properties
•Designed for time efficiency
•4 hours of run-time compared to days or weeks of run-time
•Designed to see if the problem warrants further investigation
BM 6
BM 12
Pink = 450 A/mm²
Blue = 0 to 50 A/mm²
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•Disruptions cause current to flow through blanket module
•Currents can impart JxB forces on module
•Currents become un-balanced due to connections between shield block and vacuum vessel
Note: size and direction of arrows indicate direction and magnitude of current.
Currents in Blanket Module 12
Circulating Current
Vacuum vessel interface
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Currents in Blanket Module 12Interface between shield block and vacuum vessel
Blue areas are conducting strips
(Not shown)
Arrows indicate magnitude and
direction of current
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Currents in Blanket Module 6
Interface between shield block 6 and Vacuum Vessel
Blue areas are conducting strips (Not shown)
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Currents in Blanket Module 6 Components
•Major currents flowing from vessel, to strips, through shield block, through strips, then back to vessel
•Unexpected current flow
•Merits further investigation
•Current density of 150 A/mm² in strips•Minimal current in hydraulic connector
Vacuum Vessel Interfacing
Shield block interfacing
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Current with one conducting strip
Shield-block interfacing side
•Current flowing in to and out of the same conducting strip from shield block
•Unexpected results
•Merits further investigation
•Minimal current flowing through hydraulic connector
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BM6 Strip Current
0
2000000
4000000
6000000
8000000
10000000
12000000
0 1 2 3Time (ms)
Cur
rent
(A)
Current ramps up to 11MA in milliseconds
Potential to generate massive forces
Current in BM 6 Conducting Strips
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BM6 Force
0.0E+00
5.0E+05
1.0E+06
1.5E+06
2.0E+06
2.5E+06
3.0E+06
0 0.5 1 1.5 2 2.5 3time (ms)
Forc
e(N
)
BM6 Torque
0.0E+00
1.0E+04
2.0E+04
3.0E+04
4.0E+04
5.0E+04
0 0.5 1 1.5 2 2.5 3time (ms)
Torq
ue(N
-m)
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Conclusion
Interesting results
Problem warrants further investigation
Next steps• Properly model B-field inside vacuum vessel• Analyze different current paths thoroughly • Include components with more intricate design
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Electromagnetic Analysis of Test Blanket Module
Tommy Holschuh
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Test Blanket Module
The Test Blanket Module is designed to produce tritium.
Deuterium is easy to get.
Tritium is needed for the fusion reaction, but harder to find.
Plasma-Facing Side
Back
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Test Blanket Module
The TBM contains PbLi as a liquid metal.
Neutrons interact with Lithium, produce tritium.
Elaborate system behind module to extract tritium.
Front
(Plasma-Facing Side)
BackLead-Lithium
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Test Blanket Module
During a disruption, the change in current produces forces on pieces of tokamak.
Need to model forces and torque on TBM
Use OPERA-3D to do Elektra E&M Transient Analysis
Toroidal Filament
Poloidal Coils
Conductors to simulate
Plasma
TBM
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Elektra AnalysisSum of Forces on Pieces of TBM
-40
-20
0
20
40
60
80
100
120
140
0 0.005 0.01 0.015 0.02 0.025 0.03 0.035 0.04 0.045 0.05
Time (s)
Forc
e (k
N)
Force - XForce - YForce - Z
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Elektra AnalysisSum of Torque on TBM
-200
-150
-100
-50
0
50
100
150
200
250
300
0 0.01 0.02 0.03 0.04 0.05
Time (s)
Torq
ue (k
N-m
)
Torque - X
Torque - Y
Torque - Z
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Elektra Analysis
Sum is a little high, but near expected values.
This is the sum of Force and Torque on every piece of the Test Blanket Modules (blue-colored).
These do not include frame (light green) and SS plate (green).
Frame
SS316
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Elektra Analysis – Frame and PlateSum of Forces on TBM
-400
-300
-200
-100
0
100
200
300
400
500
0 0.01 0.02 0.03 0.04 0.05
Time (s)
Forc
e (k
N)
Force - XForce - YForce - ZForce - SS316 - XForce - SS316 - YForce - SS316 - ZForce - Frame - XForce - Frame - YForce - Frame - Z
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Elektra Analysis – Frame and PlateSum of Torque on TBM
-6000
-4000
-2000
0
2000
4000
6000
8000
0 0.01 0.02 0.03 0.04 0.05
Time (s)
Torq
ue (k
N-m
)
Torque - XTorque - YTorque - ZTorque - SS316 - XTorque - SS316 - YTorque - SS316 - ZTorque - Frame - XTorque - Frame - YTorque - Frame - Z
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Elektra Analysis
Plasma-Facing Side
Back
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Future
Since then, conductor properties were checked. It was found that initial current densities were incorrect. Toroidal filament was several orders of magnitude larger than
correct value. Solenoid coils were several orders of magnitude smaller than
correct value. This was adjusted. OPERA is currently re-running analysis
Correct simulations, pictures, and data will be finished by end of this week.