F usion Reactor Technology I
(459.760, 3 Credits)
Prof. Dr. Yong-Su Na
(32-206, Tel. 880-7204)
Week 1. Magnetic Confinement
Week 2. Fusion Reactor Energetics (Harms 2, 7.1-7.5)
Week 3. How to Build a Tokamak (Dendy 17 by T. N. Todd) Week 4. Tokamak Operation (I): Startup
Week 5. Tokamak Operation (II):
Basic Tokamak Plasma Parameters (Wood 1.2, 1.3) Week 7-8. Tokamak Operation (III): Tokamak Operation Mode Week 9-10. Tokamak Operation Limits (I):
Plasma Instabilities (Kadomtsev 6, 7, Wood 6) Week 11-12. Tokamak Operation Limits (II):
Plasma Transport (Kadomtsev 8, 9, Wood 3, 4)
Contents
Week 1. Magnetic Confinement
Week 2. Fusion Reactor Energetics (Harms 2, 7.1-7.5)
Week 3. How to Build a Tokamak (Dendy 17 by T. N. Todd) Week 4. Tokamak Operation (I): Startup
Week 5. Tokamak Operation (II):
Basic Tokamak Plasma Parameters (Wood 1.2, 1.3) Week 7-8. Tokamak Operation (III): Tokamak Operation Mode Week 9-10. Tokamak Operation Limits (I):
Plasma Instabilities (Kadomtsev 6, 7, Wood 6) Week 11-12. Tokamak Operation Limits (II):
Plasma Transport (Kadomtsev 8, 9, Wood 3, 4) Week 13. Heating and Current Drive (Kadomtsev 10)
Week 14. Divertor and Plasma-Wall Interaction
3
Contents
Objectives of the Tokamak Operation
• High <n
e>/n
GW• High β
N• High H
98(y,2)
• Pulse length
Objectives of the Tokamak Operation
fishbones (q=1)
Ip (MA)Pnbi (MW)
βN
H98 (y,2)
<ne>/nGW Dα
4xli
# 14521
• No sawteeth, good confinement, and β
N~ 3.5, T
i~ T
e,
<n
e>/n
GW~ 0.88, averaged over 3.6 seconds (~ 50 τ
E).
5Objectives of the Tokamak Operation
fishbones (q=1)
Pnbi (MW)bN
H98 (y,2)
<ne>/nGW 4xli
~ 18 MW / m2 ≤ 6 MW / m2
outer divertor
inner divertor
Small ELMs
(type II)
Ip (MA) # 14521
Dα
Basic Tokamak Variables
7
•
Cylindrical and local coordinates for a tokamak
• Aspect ratio: R0/a ~ 3-5 ex) KSTAR: 3.6, ITER: 3.1
Basic Tokamak Variables
• Elongation: κ
• Triangularity: δ
• Squareness: ζ
•
Plasma equilibrium parameters
Basic Tokamak Variables
9
• Elongation
•
Plasma equilibrium parameters
a
= b
κ a
d c
2
= + δ
• Triangularity
( )
θ κ
θ δ
θ sin
sin
0
cos a Z
a R
R
=
− +
=
Basic Tokamak Variables
• Outer and inner squareness: ζo,i
•
Plasma equilibrium parameters
What is the squreness?
( )
( θ ζ θ )
κ
θ δ
θ
2 sin sin
sin sin
cos
,
1 0
i
a o
Z
a R
R
+
=
+ +
=
−Basic Tokamak Variables
11
• Separation of plasma from wall by a limiter and a divertor
• Advantage of the divertor configuration
- First contact with material surface at a distance from plasma boundary - Reducing the influx of ionized impurities into the interior of the plasma
by diverting them into an outer „SOL“
Strike point
If no limiter and divertor?
Plasma diffusing into
the whole vessel along the magnetic
field → if touching the
wall, impurities coming out
Basic Tokamak Variables
Major Radius, R0 Minor Radius, a Plasma Current, IP Elongation, κx Triangularity, δx Toroidal Field, B0 Pulse Length
Fuel
Parameters
1.8 m 0.5 m 2.0 MA 2.0 0.8 3.5 T 300 s H, D
KSTAR
6.2 m 2.0 m 15 MA 1.85 0.5 5.3 T 500 s D, T
ITER • Plasma shape
•
Plasma equilibrium parameters
13
Basic Tokamak Variables
2 0
/ 2 μ p B β =
z The ratio of the plasma pressure to the magnetic field pressure
z A measure of the degree to which the magnetic field is holding a non-uniform plasma in equilibrium.
magnetic pressure
plasma pressure
•
Beta
Basic Tokamak Variables
2 0
/ 2 μ p B β =
•
Beta
magnetic pressure plasma
pressure
Instability
(bad curvature region)
www.waterrocket.com/goachaik-28.htm the43sunsets.tistory.com/tag/코카콜라
15
Basic Tokamak Variables
2 0
/ 2 μ p B β =
z The power output for a given magnetic field and plasma assembly is proportional to the square of beta.
z In a reactor it should exceed 0.1 – economic constraint
•
Beta
r B NI
π μ
= 2
Basic Tokamak Variables
•
Beta
∫ ∫
=∫
= a p r rdr
dS a pdS
p
0
2 ( )
/ 2
π π
Assuming that the magnetic surfaces have concentric, circular CXs and that conditions are independent of ϕ.
0 0
0 0 0
0
/ 2
2
) (
, )
1 (
μ π
π
μ μ μ
θ ϕ
ϕ θ
ϕ θ
a a
p
r
aB rdr
j I
r d r r r j
B j
r rB r
j B
∫
∫
=
=
′
′
= ′
∂ =
∂
=
×
∇G G G
Ampère’s law
Basic Tokamak Variables
•
Normalized beta – stability limit
17
• Fundamental elements for the βN-limit
1. Current profile 2. Pressure profile 3. Plasma shape 4. Stabilising wall
5. Resistive instability
p t t
N
I
β aB
β =
Basic Tokamak Variables
•
Normalized beta – stability limit
• High βN in KSTAR
1. Strong plasma shaping 2. Passive stabilizers
3. PF/CS system capability 4. High heating power
5. RWM control coils