Preliminary Conceptual Design Study
of K-DEMO
Japan-US Workshop
February 26th, 2013
Advanced Project Division
National Fusion Research Institute
kkeeman@nfri.re.kr
Introduction
Advanced Project Division
Mid-Entry Strategy in 1995
Conventional Device (Cu)
Superconducting Device
ITER
DEMO
1GW
JET
1MW
Fusion Power
KSTAR
TFTR
JT-60U
JET
TFTR
1KW
PDX
JET/TFTR
DIII-D
DIII
SC Device
PLT
ALCATOR C
1W
1965
T-3
(1968)
1970
ATC
ALCATOR A
1975
1980
KAIST-T
KT-1
SNUT-79
1985
1990
1995
2000
2005
2010
2015
2020
2040
Year
3
Advanced Project Division
KSTAR Superconducting Tokamak
Advanced Project Division
KSTAR Device for 2012 Campaign
2* ECE-I + MIR (POSTECH, UCD)
VUV (ITER KO)
FIR
Thomson, 5 J, 100 Hz (JAEA, NIFS)
Reflectometer
BES (8X8) (RMKI)
Image Bolometer (NIFS)
Div. IRTV
NBI-1 2nd
100 keV, 2 MW, 10 s
NBI-1 1st
100 keV, 1.5 MW, 10 s
(KAERI, JAEA)
5
MD, Probes
Da, VS, Filterscope (ORNL)
XICS, CES (NIFS), ECE (KAERI, NIFS)
BES (RMKI), CI/2D MSE (ANU),
Interferometer, Bolometer (NIFS)
SXR (KAIST), XPH (KAIST)
Fast ion loss, Neutron (Hanyang U, ITER KO)
ECH
84 GHz / 110 GHz
0.3 MW, 2 s
ICRF
30-60 MHz,
1 MW, 1 s
(POSTECH, GA)
(KAERI)
LHCD
5 GHz, 0.5 MW, 1 s
RMP PS
4 kA/t (n=1, 2)
ECH (170 GHz)
0.7 MW, cw
(JAEA, PPPL)
Advanced Project Division
KSTAR In-vessel Control Coil System (3-D)
 Modular 3D field coils (3 poloidal x 4 toroidal)
- all internal and segmented with saddle loop configurations
- 8 conductors in each coil
- Control capability : vertical control, radial control, error correction, RMP,
RWM
 Wide spectra of Resonance Magnetic Perturbations (RMP) are possible
- n=1 RMP (phase angles : +90, -90, 180, 0) and n=2 RMP (even or odd
parity)

n=1, +90 phase
+
+
-
+
-
-
n=2, even parity
-
-
top
+
-
+
-
top
+
-
mid
-
+
-
+
mid
+
+
bot
+
-
+
-
bot
-
top
BP

n=1, 0 phase
Schematics of IVCC and its conductor
n=2, odd parity
+
+
-
-
top
+
+
-
-
mid
+
+
-
-
bot
+
-
+
mid
-
+
-
+
bot
Advanced Project Division
βN-limit and ELM Suppression
 KSTAR reached βN〉2.5 and βN/li〉 4.0
“no-wall limit” in H-mode Operation
 ELM suppressed by n=1 RMP
(Ip = 600 kA, BT=1.6~2.3T)
# 6123
Hα/
RMP
2012 New Data
2.7s
3.4s
4.3s
Advanced Project Division
Fusion Energy Development Promotion Law (FEDPL)
To establish a long-term and sustainable legal framework for
fusion energy development phases.


To promote industries and institutes which participating the
fusion energy development by supports and benefit.

The first country in the world prepared a legal foundation in
fusion energy development.
 History of the FEDPL
• 1995. 12 : National Fusion R&D Master Plan
• 2005. 12 : National Fusion Energy Development Plan
• 2007.
• 2007.
• 2007.
• 2012.
8
3 : Fusion Energy Development Promotion Law
4 : Ratification of ITER Implementation Agreement
8 : Framework Plan of Fusion Energy Development
(The first 5-Year Plan)
1 : The 2nd 5-year plan has begun
Advanced Project Division
Vision and Goal of Fusion Energy Development Policy
Vision
Secure sustainable new energy source by technological
development and the commercialization of fusion energy
Phase
Phase 1 (’07~’11)
Phase 2 (’12~’21)
Phase 3 (’22~’36)
Policy Goal
Establishment of a foundation
for fusion energy development
Development of core
technology for DEMO
Construction of DEMO by
acquiring construction capability
of fusion power plants
 Acquisition of operating technology
for the KSTAR
Basic
Directions
Basic
Promotion
Plan
Policy Goal
for Plan-2
Primary
Strategy for
Plan-2
 Participation in the international joint
construction of ITER
 Establishment of a system for the
development of fusion reactor
engineering technology
Basic Promotion Plan 1 (’07~‘11)
 High-performance plasma operation in
KSTAR for preparations for the ITER
 Completion of ITER and acquisition
of core technology
 Developmentof core technology for the design
of DEMO
Basic Promotion
Plan 2 (‘12~‘16)
Basic Promotion
Plan 3 (‘17~‘21)
 DEMO design, construction, and
demonstration of electricity production
 Undertaking of a key role in ITER
operations
 Completion of reactor core and system
design of the fusion power reactor
 Commercialization of fusion technology
Basic
promotion
plan 4
(‘22~‘26)
Basic
promotion
plan 5
(‘27~‘31)
Basic
promotion
plan 6
(‘32~‘36)
R&D for DEMO Technology based on KSTAR and ITER
Attainment of KSTAR high-performance plasma and development of
DEMO basic technology
Basic research in fusion and cultivation of man power
International cooperation and improvement of status in ITER operations
Commercialization of fusion/plasma technology and promotion of social
acceptance
Advanced Project Division
Korean Fusion Energy Development Roadmap
“Key Milestones”
Pre-Conceptual DEMO R&D
Launch &
Design Study
CDA
DEMO Phase-1
DEMO EDA DEMO Final
10
Start Design & Constr. Construction Finish
Start
Advanced Project Division
K-DEMO Tokamak Design
Advanced Project Division
General Requirement (Two Phase Operation)







K-DEMO has two operation phases, Phase I and Phase II. Though the operation phase I K-DEMO does
not need to demonstrate the competitiveness in COE(Cost of Electricity), the operation phase II KDEMO need to demonstrate the competitiveness in COE.
All power core and plant subsystems in K-DEMO plant must be representative of those in the
commercial plant. Extrapolation of technologies from K-DEMO to a commercial reactor should be
straight forward. Practically all technologies to be used in commercial reactors should be
demonstrated in the K-DEMO. Also, extrapolation of performance parameters between K-DEMO and
commercial reactors should be minimized.
K-DEMO shall be operated and maintained with remote handling equipment. This is an absolute
prerequisite as the neutron level during operation and radioactive activation during maintenance
periods will be excessive for human intervention inside the power core building and hot cell bioshields at all times
The operation phase II K-DEMO plant need to achieve an overall all plant availability larger than 70%.
The operation phase I K-DEMO is not considered as the final DEMO. It is a kind of test facility for a
commercial reactor. But the operation phase II K-DEMO will require a major up-grade by replacing
the blanket & divertor system and others if required.
Construction cost for K-DEMO should be minimized and the size of the K-DEMO Tokamak is
expected to be smaller or similar size of ITER Tokamak.
The operation phase I K-DEMO
•
•
•

At initial stage, many of ports will be used for diagnostics for the operation and burning plasma physics study, but many of
them will be transformed to the CTF (Component Test Facility).
At least more than one port will be designated for the CTF including blanket test facility.
It should demonstrate the net electricity generation (Qeng > 1) and the self-sufficient Tritium cycle (TBR > 1.05).
The operation phase II K-DEMO
•
•
Though there will be a major upgrade of In-Vessel-Components, at least one port will be designated for CTF for future studies.
It is expected to demonstrate the net electricity generation larger than 450 MWe and the self-sufficient Tritium cycle .
Advanced Project Division
Optimization Concept of K-DEMO
 Demonstrate a reasonable net-electricity (> 300 MW) generation
with a minimum cost
 Provide a maximum flexibility
8
βN
6
ARIES-AT
CREST
4
ARIES-RS
K-DEMO (Stage II)
PPCS-D
SSTR
K-DEMO (Stage I)
ITER
2
0
4
6
8
10
12
BT(T)
Advanced Project Division
K-DEMO Design Parameters
Basic Parameter
Option I
Option II
Option III
Major Radius
6.0 m
6.65 m
7.15 m
Minor Radius
1.8 m
2.0 m
2.2 m
Elongation (k95)
1.8
Magnetic Field (Bo)/Peak Field
7.5 Tesla / ~ 16 Tesla
Divertor Type
Double Null (or Single Null)
Bootstrap Current Fraction
~ 0.6
Normalized beta
~ 4.0
Safety Factor (q95)
3.5~5.0
Plasma Current
> 10 MA
> 12 MA
> 13 MA
Total Fusion Power (Neutron)
1700 MW
2130 MW
2721 MW
Q-value
24
27
30
Total H&CD Power
70 MW
80 MW
90 MW
Thermodynamic Efficiency
0.35
Gross Electric Power
767 MW
958 MW
1220 MW
Recirculating Fraction
0.7
0.6
0.55
Recirculating Electric Power
537 MW
575 MW
671 MW
Net Electric Power
230 MW
383 MW
549 MW
Advanced Project Division
DEMO TF CICC Parameter(Helical Spiral)
 Cable Pattern: (3SC)x4x6x6x(5+Spiral)[2160 SC strand]
 Void Fraction : 28.85%
 Strand :
High Jc (> 2600A/mm2) Nb3Sn Strand
Cu/Non-Cu = 1.0
R3
 Helical Spiral : ID = 8 mm OD = 12 mm
 Insulation : 1.6 mm (with Voltage Tap)
0.1 mm Kapton 400%
0.3 mm S-glass 400%
 Jacket Thickness : 5.0 mm
 Twist Pitch
•
•
•
•
•
1st Stage 45 ± 5 mm
2nd Stage 85 ± 10 mm
3rd Stage 125 ± 15 mm
4th Stage 245 ± 20 mm
5th Stage 435 ± 20 mm
 Wrapping Tape Thickness
•
•
•
•
5.0
Insulation
Jacket
70.8
74.0
•
•
1.6
60.8
•
•
30.8
40.8
44.0
Sub-cable : 0.08 m 40%
Sub-cable wrap width : 15 mm
Cable : 0.08 mm 140%
Final wrap width : 40 mm
 SC Strand Weight : ~600 ton
DEMO TF CICC Cross-section
Advanced Project Division
DEMO Small TF CICC Parameter
 Cable Pattern: (3SC)x4x5x(6+Central Spiral)[360 SC strand]
 Void Fraction : 31.03%
 Strand :
High Jc (> 2600A/mm2) Nb3Sn Strand
Cu/Non-Cu = 1.0
 Central Spiral : ID = 7 mm OD = 10 mm
 Insulation : 1.6 mm (with Voltage Tap)
0.1 mm Kapton 400%
0.3 mm S-glass 400%
 Jacket Thickness : 5.0 mm
 Twist Pitch
•
•
•
•
1st Stage 45 ± 5 mm
2nd Stage 85 ± 10 mm
3rd Stage 125 ± 15 mm
4th Stage 335 ± 20 mm
 Wrapping Tape Thickness
•
•
•
•
Sub-cable : 0.08 m 40%
Sub-cable wrap width : 15 mm
Cable : 0.08 mm 200%
Final wrap width : 40 mm
1.6
5.0
R3
Insulation
34.0
•
•
20.8
30.8
•
•
Jacket
20.8
30.8
34.0
DEMO TF CICC Cross-section
Advanced Project Division
Inboard Cross-Section of TF Coil (Option I)
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



R = 6.0 m, a = 1.8 m
Small CICC Coil : 16 x 8 turns Large CICC Coil : 12 x 5 turns (Total : 188 turns)
Magnetic Field at Plasma Center : ~7.72 Tesla (Bpeak ~ 16 Tesla, T-margin > 1 K)
Nominal Current : 77.0 kA
Conductor Length :
•
•
LQP = ~777 m (Quadruple Pancake) Total : ~445 tons
SDP = ~634 m (Double Pancake) Total : ~163 tons
Clearance
Filled with
Glass Fiber
(5 mm)
Ground Wrap
(5 mm)
2050 mm
2388 mm
2660 mm
2890 mm
2970 mm
Advanced Project Division
Outboard Cross-Section of TF Coil (Option I)
Ground Wrap
(5 mm)
Space (Filled with
316) for Turn
Transition and Feed
Through
(90 mm)
550 mm
106 mm
Clearance
Filled with
Glass Fiber
(5 mm)
278 mm
870mm
10910 mm
10990 mm
11210 mm
112310 mm
198 mm
11582 mm 11780 mm
Advanced Project Division
Inboard Cross-Section of TF Coil (Option II)





R = 6.5 m, a = 2.0 m
Small CICC Coil : 18 x 8 turns Large CICC Coil : 12 x 5 turns (Total : 204 turns)
Magnetic Field at Plasma Center : ~7.72 Tesla (Bpeak ~ 16 Tesla, T-margin > 1 K)
Nominal Current : 76.9kA
Conductor Length :
•
•
LQP = ~825 m (Quadruple Pancake) (Total : ~480 ton)
SDP = ~680 m (Double Pancake) (Total : ~200 ton)
Clearance
Filled with
Glass Fiber
(5 mm)
Ground Wrap
(5 mm)
2150 mm
2633 mm
2905 mm
3135 mm
3220 mm
Advanced Project Division
Outboard Cross-Section of TF Coil (Option II)
106 mm
Clearance
Filled with
Glass Fiber
(5 mm)
Space (Filled with 316)
for Turn Transition
and Feed Through
(90 mm)
11810 mm
550 mm
Ground Wrap
(5 mm)
244 mm
880 mm
11895 mm
12115 mm
12215 mm
203 mm
12487 mm
12690 mm
Advanced Project Division
DEMO TF CICC Parameter(Option II-A)
 Cable Pattern: (3SC)x4x5x6x(5 + Helical Spiral) [1800 SC strand]
 Void Fraction : 28.1%
 Strand :
•
•
High Jc (> 2600A/mm2) Nb3Sn Strand
Cu/Non-Cu = 1.0
R3
 Helical Spiral : ID = 8 mm OD = 12 mm
1.6
 Insulation : 1.6 mm (including Voltage Tap)
 Jacket Thickness : 5.0 mm
 Twist Pitch
•
•
•
•
•
1st Stage 45 ± 5 mm
2nd Stage 85 ± 10 mm
3rd Stage 125 ± 15 mm
4th Stage 245 ± 20 mm
5th Stage 435 ± 20 mm
 Wrapping Tape Thickness
•
•
•
•
Insulation
68.8
72.0
0.1 mm Kapton 400%
0.3 mm S-glass 400%
58.8
•
•
5.0
Jacket
26.8
36.8
40.0
Sub-cable : 0.08 m 40%
Sub-cable wrap width : 15 mm
Cable : 0.08 mm 140%
Final wrap width : 40 mm
DEMO TF CICC Cross-section
Advanced Project Division
Inboard Cross-Section of TF Coil (Option II-A)






Selected for Detailed Study
R = 6.8 m, a = 2.1 m
Small CICC Coil : 20 x 9 turns Large CICC Coil : 12 x 5 turns (Total : 240 turns)
Magnetic Field at Plasma Center : ~7.4 Tesla (Bpeak ~ 16 Tesla, T-margin > 1 K)
Nominal Current : 65.52 kA
Conductor Length :
•
•
LQP = ~872 m (Quadruple Pancake) (Total : ~418 ton)
SDP = ~810 m (Double Pancake) (Total : ~258 ton)
Clearance
Filled with
Glass Fiber
(5 mm)
Ground Wrap
(5 mm)
2150 mm
2619 mm
2925 mm
3135 mm
3220 mm
Advanced Project Division
Outboard Cross-Section of TF Coil (Option II-A)
118 mm
Clearance
Filled with
Glass Fiber
(5 mm)
Space (Filled with 316)
for Turn Transition
and Feed Through
(120 mm)
12210 mm
550 mm
Ground Wrap
(5 mm)
210 mm
925 mm
12295 mm
12525 mm
12655 mm
204 mm
12961 mm 13165 mm
Advanced Project Division
Inboard Cross-Section of TF Coil (Option III)





R = 7.15 m, a = 2.2 m
Small CICC Coil : 18 x 8 turns, Large CICC Coil : 12 x 6 turns (Total : 216 turns)
Magnetic Field at Plasma Center : ~7.5 Tesla (Bpeak ~ 16 Tesla, T-margin > 1 K)
Nominal Current : 77.6 kA
Conductor Length :
•
•
LQP = ~ 1102 m (Quadruple Pancake) (~643 ton)
SDP = ~ 763 m (Double Pancake) (~218 ton)
Clearance
Filled with
Glass Fiber
(5 mm)
Ground Wrap
(5 mm)
2385 mm
2849 mm
3121 mm
3395 mm
3480 mm
Advanced Project Division
Outboard Cross-Section of TF Coil (Option III)
955 mm
550 mm
Ground Wrap
(5 mm)
Space (Filled with 316)
for Turn Transition
and Feed Through
(120 mm)
244 mm
106 mm
Clearance
Filled with
Glass Fiber
(5 mm)
13025 mm
13110 mm
13374 mm
13504 mm
204 mm
13776 mm
13980 mm
Advanced Project Division
Joint Scheme of Inner Magnet
From PS (or Inner Magnet Lead)
Inter Coil Joint
Helium
Feed Through
Inter Coil Joint
Layer Transition
Layer Transition
Layer Transition
To Neighboring Inner Magnet Lead
Advanced Project Division
Joint Scheme of Outer Magnet
From Outer (or Last Inner) Magnet Lead
To Neighboring Outer Magnet Lead
Advanced Project Division
3D Modeling of TF Magnet
Advanced Project Division
3D Modeling of TF Assembly
Advanced Project Division
TF Coil Structure
Advanced Project Division
DEMO CS CICC Parameter (Corner Channel)
 Cable Pattern: (3SC)x3x4x4x6 [864 SC strand]
 Void Fraction : 37.19%
 Strand :
ITER Type (Jc ~ 1050A/mm2) Nb3Sn Strand
Cu/Non-Cu = 1.2
 NO COOLING SPIRAL  Corner Channel
 Jacket Thickness : 5 mm
 Insulation : 2.0 mm (with Voltage Tap)
•
•
•
•
•
•
•
1st Stage 45 ± 5 mm
2nd Stage 85 ± 10 mm
3rd Stage 145 ± 10 mm
4th Stage 250 ± 15 mm
5th Stage 420 ± 20 mm
 Wrapping Tape Thickness
•
•
•
•
2
0.1 mm Kapton 400%
0.4 mm S-glass 400%
 Twist Pitch
Sub-cable : 0.08 mm 40%
Sub-cable wrap width : 15 mm
Cable : 0.5 mm 60%
Final wrap width : 7 mm
R3
Insulation
Jacket
5
40
50
54
•
•
34
30
20
DEMO CS CICC Cross-section
Advanced Project Division
Cross-Section of CS Coils (Option I)
1296 mm
Number of Turns : 14 (Total SC strand weight : ~120 tons)
Number of Layers : CS1 & CS2 : 30 layers, CS3 : 24 layers
Magnetic Field at Center : ~12.52 Tesla (Bpeak < 12.774 Tesla)
Conductor Unit Length : 895 m (CS1 & CS2 : UL x 5, CS3 : UL x 4)
Gap Between Coils : 50 mm
1620 mm





1420 mm
1420 mm
CS1 & CS2 Coil
1896 mm
1896 mm
CS3 Coils
Advanced Project Division
Magnetic Field of CS Coils (Option I)
 Magnetic Field
• Field at Center : ~12.835 Tesla
• Peak Field : ~ 13.086 Tesla
• Maximum Flux Swing : ~81 V·sec
 Nominal Current : 44 kA
(Current can be increased)
 Temperature Margin ~ 1.4 K
Advanced Project Division
Cross-Section of CS Coils (Option II)
Number of Turns : 14 (Total SC strand weight : ~145 tons)
Number of Layers : CS1, CS2 & CS2 : 30 layers
Magnetic Field at Center : ~13.12 Tesla (Bpeak < 13.37 Tesla)
Conductor Unit Length : 950 m (CS1, CS2 & CS3 : UL x 5)
Gap Between Coils : 50 mm
1620 mm





1500 mm
CS1 & CS2 & CS3 Coil
1976 mm
CS3 Coils
Advanced Project Division
Magnetic Field of CS Coils (Option II)
 Magnetic Field
• Field at Center : ~13.12 Tesla
• Peak Field : ~ 13.37 Tesla
• Maximum Flux Swing : ~93 V·sec
 Nominal Current : 45 kA
(Current can be increased)
 Temperature Margin ~ 1.1 K
Advanced Project Division
Cross-Section of CS Coils (Option III)
Number of Turns : 14 (Total SC strand weight : ~165 tons)
Number of Layers : CS1, CS2 & CS2 : 30 layers
Magnetic Field at Center : ~13.1 Tesla (Bpeak < 13.35 Tesla)
Conductor Unit Length : 1070 m (CS1, CS2 & CS3 : UL x 5)
Gap Between Coils : 50 mm
1620 mm





1730 mm
CS1 & CS2 & CS3 Coil
2206 mm
CS3 Coils
Advanced Project Division
Magnetic Field of CS Coils (Option III)
 Magnetic Field
• Field at Center : ~13.12 Tesla
• Peak Field : ~ 13.41 Tesla
• Maximum Flux Swing : ~123 V·sec
 Nominal Current : 46 kA
(Current can be increased)
 Temperature Margin ~ 1.1 K
Advanced Project Division
Test Samples of Conductors
DEMO CS CICC(corner channel) & Large TF CICC (helical spiral)
Thanks to Antonio della Corte & his colleagues (ENEA/ICAS) !!
Advanced Project Division
Concept of Vertical Maintenance (Pilot Plant)
 Vertical maintenance of all in-vessel components for Pilot Plant (PPPL) Case
Enlarged TF
VV (~150° C)
Semi-permanent
Inboard Shield
structure (~350° C)
Internal VV
maintenance space
expanded
Horizontal assisted
maintenance
Horizontal assisted
maintenance
DCLL PbLi/He Base
Blanket (350/450° C)
Gravity support /
coolant supply
plenum
Coolant supply
from below
Advanced Project Division
3D Modeling of Blanket System
Advanced Project Division
3D Modeling of Blanket System
Advanced Project Division
3D Modeling of Blanket System
Advanced Project Division
3D Modeling of Blanket System
Advanced Project Division
3D Modeling of Blanket System
Advanced Project Division
3D Modeling of Blanket System
Advanced Project Division
3D Modeling of Blanket System
Advanced Project Division
Assumption for the Thickness of Blanket
Inboard-Side Blanket [Thickness = 1000 mm]
FW
38
Blanket
150
50
85
200
70
240
Be
Be
167
Manifold &
Structures
Shield
W
FW
40
Structural
Material
Li4SiO4
Cooling
channel
Be
B4C
Outboard-Side Blanket [Thickness = 1225 mm]
Blanket
50
150
Be
85
200
Be
100
100
20
200
Shield
280
Manifold &
Structures
Advanced Project Division
Radial Build of K-DEMO [unit : mm] (Option I)
CS
1420
1896
2050
TF
BlanVV
ket
SOL
TS
3000
3170
3300
Plasma
Blanket
VV
SOL
Space for
Vertical
Maintenance
4100
4200
6000
7800
7900
9100
TF
TS
10100
10480
10910
11780
Advanced Project Division
Radial Build of K-DEMO [unit : mm] (Option II)
CS
1500
1976
2150
TF
BlanVV
ket
TS
3220
3420
3550
4550
4650
Plasma
SOL
Blanket
SOL
6650
8650
8750
VV
Space for
Vertical
Maintenance
9975
11175
11555
11985
TF
TS
12895
Advanced Project Division
Radial Build of K-DEMO [unit : mm] (Option II-A)
CS
1500
1976
2150
TF
BlanVV
ket
TS
3220
3420
3550
4600
4700
Plasma
SOL
Blanket
SOL
6800
8900
9000
VV
Space for
Vertical
Maintenance
10200
11400
11780
12210
TF
TS
13135
Advanced Project Division
Radial Build of K-DEMO [unit : mm] (Option III)
CS
1730
2206
2385
TF
BlanVV
ket
TS
3480
3680
3850
4850
4950
Plasma
Blanket
SOL
SOL
7650
9350
9450
VV
Space for
Vertical
Maintenance
10675
12175
12575
13025
TF
TS
13980
Advanced Project Division
K-DEMO Conceptual Study & CDA Schedule
2012.1~2012.12
2013.1~2013.12
2014.1~2014.12
2015.1~2017.12
2018.1~2021.12
Pre-study
Pre-study Report
Design Parameter Options
Physics & Backup Study (Phase I)
Physics & Backup Study (Phase II)
Pre-Conceptual Design Study Report
★
Improvement of Report
CDA Phase I
★
CDA Phase II + CDR
Target Date for K-DEMO Construction : End of 2037
Advanced Project Division
SUCCEX Facility
Advanced Project Division
Requirement


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Split pair solenoid magnet system
Inner bore size : ~1 m
Maximum magnetic field : ~16.39 Tesla
Magnetic field at center : ~ 15.33 Tesla
Maximum Helium flow channel length : < 100 m
• One magnet of the split pair consists of three coil (IC, MC, OC) and the
maximum of Helium channel length should be maintained below 100 m
• Every double pancake of each coil will have Helium inlet and outlet
• Each coil have a number of inter magnet joints because of the maximum
fabrication capability in the length of CICC
 Test Mode
• Semi-circle type conductor sample test mode
 U-shape sample with the bottom radius of 0.5 m
 DEMO TF conductor will have a rectangular cross-section to reduce the strain effect & will have
capability of a minimum bending radius of 0.5 m
 No joint : no question regarding voltage arising from the joint
 There are enough distance for the voltage relaxation from the sample terminal to voltage taps
• Sultan like sample test mode
 For the case of CS conductor, the size of the is expected to be a range of 50 mm. And it is not
easy to make the U-shape sample because of the minimum bending radius
 Also the facility could support the joint technology development
Advanced Project Division
Coil Parameters
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Gap Between Upper and Lower Coil : 140 mm
Operating Current : 18 kA
Peak Field : 16.39 Tesla
Center Field : 15.33 Tesla
Number of Strand per CICC
• IC : 360 strands
• MC : 244 strands
• OC : 72 strands
 Conductor Size (Including 1.0 mm insulation)
• IC : 18 x 37 mm
• MC : 16 x 30 mm
• OC : 15 x 29 mm
 Jacket Thickness
• IC : 3 mm
• MC : 3 mm
• OC : 2.5 mm
 Insulation : 1.0 mm Thick
• 0.1 mm Kaption (400%)  0.4 mm
• 0.15 mm S-Grass Fiber Tape (400%)  0.6 mm (include voltage tap)
Advanced Project Division
Conductor Parameter
IC (Inner Coil) CICC : (3SC)x4x5x6[360 SC strand], VF = 27.62%
MC (Middle Coil) CICC : (2SC+1Cu)x3x4x6[144 SC strand], VF = 26.96%
OC (Outer Coil) CICC : (1SC+2Cu)x3x4x6[72 SC strand], VF = 26.96%
Strand : High Jc (> 2600A/mm2) Nb3Sn (total ~ 6.5 ton)
Twist Pitch : 50 mm – 110 mm – 170 mm – 290 mm
No Sub-Cable Wrapping
18.0
16.0
1.0
3.0
IC CICC Cross-section
30.0
37.0
R3
1.0
16.0
14.0
15.0
13.0
R3
R3
3.0
MC CICC Cross-section
29.0
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1.0
2.5
OC CICC Cross-section
Advanced Project Division
Coil Parameters
 Peak Field in Each Coil
• IC : 16.39 Tesla, MC : 13.6 Tesla, OC : 7.9 Tesla
 Number of Turns per Layer
• IC : 6 turns, MC : 16 turns, OC : 13 turns
 Number of Layers
• IC : 20 layers, MC : 24 layers, OC : 24 layers
 Geometry (Excluding Ground Wrapping)
• IC : ID = 500 mm, OD = 608 mm, Height = 740 mm
• MC : ID = 648 mm, OD = 904 mm, Height = 720 mm
• OC : ID = 944 mm, OD = 1139 mm, Height = 696 mm
 Helium Channel Length
• IC : 42 m, MC : 78 m, OC : 85 m
 Required SC Strand Mass : total 5,615 kg in Coil
• Strand Diameter : 0.82 mm including 0.002 mm Cr Plating
• IC : 1.51 ton (437 m x 2), MC : 2.66 ton (644 m x 3 x 2), OC : 1.45 ton (700 m x 3 x 2)
• Strand Required including Cabling Loss : ~6.5 ton
Advanced Project Division
766 mm
500 mm
608 mm
648 mm
904 mm
944 mm
1139 mm
70 mm
790 mm
810 mm
SUCCEX Magnet Cross-Section (Upper Coil)
Advanced Project Division
Magnetic Field Profile
Advanced Project Division