TOFE 2016 [Philadelphia, 2016/08/22-25]

Recent Fusion Activities of Korea toward DEMO

Auguest 23rd, 2016

Keeman Kim, Kihak Im, H. Park, Y. K. Oh, Y. S. Kim
National Fusion Research Institute
TOFE 2016 [Philadelphia, 2016/08/22-25]

Mid-Entry Strategy : Korea, Year 1995
Conventional Device (Cu)Superconducting Device

ITER

DEMO

1GW

FIRST MOVER

JET
TFTR
JT-60U

Fusion Power

1MW

JET
TFTR

KSTAR
FAST FOLLOWER

JET/TFTR

DIII-D

1KW

PDX

DIII

PLT

Superconducting Device

ALCATOR C

1W

1965

T-3
(1968)

1970

ATC

ALCATOR A

1975

KAIST-T
KT-1

SNUT-79

1980

1985

1990

1995

2000

2005

2010

2015

2020

2040

Year
2
2

TOFE 2016 [Philadelphia, 2016/08/22-25]

KSTAR and ITER Project3

TOFE 2016 [Philadelphia, 2016/08/22-25]

KSTAR Mission and Key Parameters Achieved key parameters
 KSTAR missions
 To achieve the superconducting tokamak
Achieved
Parameters
Designed(~2015)construction and operation experiences
 To explore the physics and technologies
of high performance steady-state
operation that are essential for ITER andfusion reactor

High beta
advanced scenario

H-modesteady-state
KSTAR
4

DEMO

Major radius, R0

1.8 m

1.8 m

Minor radius, a

0.5 m

0.5 m

Elongation, 

2.0

1.8

Triangularity, 

0.8

0.8

Plasma shape

DN, SNDN, SN

Plasma current, IP

2.0 MA

1.0 MA

Toroidal field, B0

3.5 T

3.5 T

H-mode duration

300 s

55 s

N

5.0

4.0

Superconductor

Nb3Sn, NbTi

Nb3Sn, NbTi

Heating /CD~ 28 MW~ 10 MWPFC

C, CFC, W

C, (W)ITER
TOFE 2016 [Philadelphia, 2016/08/22-25]

KSTAR Superconducting Tokamak

2008

2009

2012
5

TOFE 2016 [Philadelphia, 2016/08/22-25]

2010

KSTAR Device and Key Components
Heating &CD in 201510.3 MW

Planned H&CD
: 28 MWNBI
5.5 MW on-axis (50s)

NBI (2018)
8 MW on-axis (300s)
4 MW off-axis (300s)

ECH/CD
1 MW 170 GHz (50s)
1 MW 105/140 GHz
LHCD
0.5 MW 5 GHz
ICRF
2 MW 30-60 MHz
Helicon CD
0.3 MW 0.5 GHz

ECH/CD
3 MW 105/140 GHz (300s)
3 MW 170 GHz (300s)
LHCD
4 MW 5 GHz (300s)

ICRF/ICWC
2 MW 30-60 MHz
Helicon CD
4 MW 0.5 GHz (300s)

Diagnostics
Magnetic & Probes
Thomson / ECE
D / Bolometer
Interferometer / Reflect.
Visible TV / IRTVECEI / MIR / RFSoft X-ray & Hard X-ray
CES / BES (D & Li)
MSE / XICSPWI research

Graphite PFC
W-bond marker tiles
Deposition & erosion
3D field research
In-vessel coils(4 x 3 module)
Broadband power supply

TOFE 2016 [Philadelphia, 2016/08/22-25]

Brief history of KSTAR operation
2015. Longest H-mode record(~ 55s at 0.6 MA)
Fully non-inductive SS operation (P ~3.5)
Stationary ELM-crash suppression (~10s)
2014. Longest H-mode record(~ 45s at 0.6 MA)
Large current H-mode (1 MA, 9s)
Low q95 operation (q95~2.0, Ohmic)
High normalized  operation (N ~4.0, transient)2013. verify Lowest Intrinsic Error field (~1 x 10-5)
2011. ELM-crash suppression using RMP(Unique in ELM-crash suppression using n=1 RMP)
2010. H-mode discharge (Ip ~0.6 MA, PNBI ~1 MW)(First H-mode in superconducting tokamak)2008. First plasma achievement (Ip >100 kA, BT ~1.5 T)(Validation of ECH pre-ionization in 2nd harmonics)
7

TOFE 2016 [Philadelphia, 2016/08/22-25]

ITER relevant Physics Program in KSTAR based on
KSTAR Uniqueness Uniqueness of KSTAR device

Lowest error field and magnetic ripple
ITER relevant IVCC (top, middle and bottom)
The most advanced diagnostic systems
High beta will be realized with 2nd NBI in2018

 Current ITER relevant researches





8

Long-pulse steady-state discharges : Hmode (> 55 s), high beta, hybrid ..
ELM crash control with IVCC (fullsuppression for >10s)
NTM control with ECH
Disruption control

TOFE 2016 [Philadelphia, 2016/08/22-25]

Excellent Testbed for Toroidal Symmetry of the
Plasma in KSTAR Lowest intrinsic error field (dB/B0 ~ 1x10-5) may allow higher
stability limits Magnetic ripple is the lowest by design (dB/B0 ~ 5x10-4) : better
trapped particle confinement and edge physics

Standard compass scan of error field(Y. In, NF, 2015)
Measured intrinsic error field
9

TOFE 2016 [Philadelphia, 2016/08/22-25]

Versatile Magnetic Perturbation Control System
 Magnetic perturbation (n=1,2) with variety of phase and amplitude by IVCC
 In KSTAR, ELM-crash suppression has been demonstrated with MP inducedby IVCC (n=1,2) with variety of phase and amplitude
 3D field research capability using in-vessel control coils & broadband power
supplies

ELM-crash suppression using RMP

Various mode and phase configuration
10

New broadband power supply and patch
panel for In-vessel control coils

TOFE 2016 [Philadelphia, 2016/08/22-25]-10-

Long-pulse Reliable Operation of NBI System
 Reliable operation of the 1st NBI in long-pulse : 5.5 MW (12s), 4.2 MW (55s) Construction of the 2nd NBI for high beta (6 MW off-axis, 2 MW on-axis)
 Long-pulse operation of ECH/CD systems : 170 GHz, 1 MW (50s)

NBI-1

Long-pulse operation of NBI-1

NBI-2
11

Design of off-axis NBI-2

TOFE 2016 [Philadelphia, 2016/08/22-25]

Long-pulse operation of
170 GHz ECCDSystem upgrade for 2015 & 2016 campaigns
In-vessel Components••

Magnetics and electricity

Demonstration of active watercooling for PFC & divertor (‘15)
Preparing Pellet injection and Invessel cryopump (’16)••

Broadband IVCC Power Supplies
Normal operation of Motorgenerator
Heating & CDUpper
divertor (nocooled)

•
•
•

Lower
divertor(watercooled)

Diagnostics••

Comparison of PFC temperature between
no-cooled and water cooled divertors

Prototype Helicon Current Drive
system operation (0.5 GHz)
Installation 1 MW, 105/140 GHz
ECH/CD system (‘16)
Approval of NBI-2 (6 MW, on-and
off-axis) construction (’18)

Laser Replacement of Thomson
Scattering
Commissioning of MSE diagnostics
for current profile measurement

TOFE 2016 [Philadelphia, 2016/08/22-25]

Recent ITER relevant Research toward Long-pulse
H-mode Discharges■ Long-pulse H-mode discharge in 2015
up to 55s (0.6 MA), final goal : 300 s■ Large plasma current H-mode discharge
in 2015 up to 1 MA, final goal : 2 MA

• Ip = 0.6 MA, BT=2.9T, tHmode~56s,• PNBI ~ 3.0 MW, PECH ~ 0.6 MW,
Shot 14326

Zp & Rp-1.8 [m]Elongation ~ 1.7, li ~ 1

0.6 MA, 55s
ne : 4-5 1019 m-3

betaN & betaP ~ 1.2-1.5

q95 ~ 7 (BT =2.9 T / Ip = 0.6 MA, kappa ~ 1.7)
0

13

10

20

30

Time [s]4050TOFE 2016 [Philadelphia, 2016/08/22-25]

1.0 MA

Exploring the advanced high performance
scenarios development■ Fully non-inductive, steady-state Hmode discharge has been achieved
up to 12s at 0.4 MA• Ip = 0.4 MA, BT=2.9T• PNBI ~ 5.1 MW, PECH ~ 0.5 MW• p  3.5 ( N  2.0 ), H89  2.2■ High beta (N ~ 4.0) operation exceeding
ideal n=1 no wall limitN ~ 4.0#13008Loop voltage ~ 0 V, 12s

p  3.5■ Extremely low q95 (q95 ~ 2.0) operation
verifying extremely low error field

Q95 < 2.0
w/o external field
w/ external field
10

TOFE 2016 [Philadelphia, 2016/08/22-25]

Edge Localized Mode (ELM) -crash suppression
using low-n error field uniquely in KSTAR■ KSTAR is unique device showing the ELM-crash suppression at various
combination of RMP fields at low n configuration (n=1 and n=2) .
• Successful ELM suppression at low n could be related to low error field.
• Check the possibility of the ex-vessel control as for ELM control in ITER and DEMO
Stationary ELM-crash suppression at
n=1 ( > 10s)

Marginal ELM-crash suppression
at n=2 ( > 10s) in 2015

ELM-crash suppression (>10s)

ELM-crash suppression (>10s)

+ + -

-

- + + -

+ - + -

- - + +
n=1 (+90 phasing)
15

TOFE 2016 [Philadelphia, 2016/08/22-25]

n=2 (mid-frame)Advanced 2D/3D Imaging Diagnostics
ELM-ing Phase
HFS

LFS

• Most powerful tools to interpret the
dynamics in fusion plasma• ECEI, MIR, BES, MSE diagnostics are
unique diagnostics in KSTAR
16

TOFE 2016 [Philadelphia, 2016/08/22-25]

Validation q0 in Sawtooth Instability
No ECCD

J. Ko (MSE, 2015)

ECCD atr/a= 0.27

 Sawtooth with no current blip only has 1/1 mode justbefore the crash Initial excitation of the 3/3 mode with current blip at
r/a=0.27 suggests q0 >1.0 after the crash Transformation of the 3/3 mode into 2/2 modesuggests the current blip moves toward the center Transformation of the 2/2 mode into the 1/1 kink modesuggests q0 drops below ~1.0 before the crash Results are consistent with those from the M3Dc1
code
17

TOFE 2016 [Philadelphia, 2016/08/22-25]

Global Simulation of the ELM (MHD vs. Kinetic)n = 12 simulation(XGC1)- kinetic
Collision is notincluded

Z (m)(BOUT++) - MHD

n = 12 simulation• KSTAR #9380

Controversies in 1) Mode intensity
2) Mode number 3) Rotation direction
cast a doubt in PB modeling
M. Kim, and Xu
18

Kinetic (XGC1) results are closer tothe measurement
TOFE 2016 [Philadelphia, 2016/08/22-25]

R (m)C.S. Chang,
S. Ku, M. Kim

Challenge for Unresolved Physics Issues
ELM-ing Phase
HF
LFS
S

 Dynamics of ELMs and ELM crashsuppression with RMP
Measurements are beyond H-alphaand magnetics

Interaction between turbulence
induced by RMP and ELMs

Global ELM (HFS and LFS) points PB
model is not sufficient
4

#
1
1 0
4 1
. 8
5 6

6

4

3

2

2

14.5

PRL 2016 (J.H. Lee, UNIST)
19

TOFE 2016 [Philadelphia, 2016/08/22-25]

R
6 4M2 0
P

234



15

1
5

15.5

1
Tim
5
e [s]
.
5

16

1
6

16.5

1
6
.
5

0
17

1
7

Fusion R&D collaboration network in Korea
Fusion Plasma Stability andconfinement ResearchCenter

UNIST /POSTECH/ PU

Three core research centers
and universities supporting
the basic fusion researchand HR development

Impurity and Edge
Research Center

KAIST /HYU/ SNU

KSTAR

Universities &Research Institutes

Center for Advanced
Tokamak Study

SNU /KAERI

20

Hanyang U.
Daegu U.
Ajou U.
Jeju N.U.
KAERI
UST

TOFE 2016 [Philadelphia, 2016/08/22-25]

Yonsei U.
Dankook U.
Chonbuk N.U.
Kyungpook N.U.
Chungnam N.U.

Worldwide collaborators in the KSTAR researchand experiments
International Collaborators
•
•
•
•
•
•
•
•
•
•

EUROfusion
IPP
CCFE
CEA
Cadarache
ENEA
WignerTU/eYork U
Politechnico
du Torino
ITER

• DOE
• Kurchatov Inst
• Gycom• PELIN• ASIPP• SWIP• HUST

•
•
•
•

JAEA
NIFS
Nagoya U.
Kyusu U.

• IPR

Korea Domestic
Collaborators

• ANU

MSIP
SNU
Hanyang U
Yonsei U
Ajou U
NST
NRF
NFRI
KODA
KAERI
KAIST
CNU
UST

21

TOFE 2016 [Philadelphia, 2016/08/22-25]

•
•
•
•
•
•
•
•
•
•
•

PPPL
Oak Ridge Nat’l Lab.
General Atomics
Columbia U.
MIT
UCSD
UC Davis
LBNL
Princeton U.
Wisconsin U
D-TACQ

KAPRA
Dankook U
KNU
Daegu UPOSTECH
UNIST
Pusan U
Chonbuk U
GIST
Jeju UCurrent and Future KSTAR Research Plan
■ Main Research Program toward the high beta steady-state operation••••

Establish the limits of the confinement and stability of tokamak plasmas through 3D
field research (KSTAR uniqueness)
Validation of MHD physics using 2D/3D imaging diagnostics to establish predictablecapability of theoretical models (M3Dc1, BOUT++, JOREK, etc.)
Validation of turbulence physics using 2D/3D imaging diagnostics to establish the
hierarchy in transport physics using gyro-fluid & gyro-kinetic simulation
For advanced steady-state operation, upgrade of the heating & CD (off-axis NBI
heating & ECH, LHCD, Helicon CD), diagnostics and control system, and density
control (active cooling divertor, pellet, in-vessel cryopump)■ Special Research Program•••

Tokamak simulator : based on validated simulation codes using KSTAR as testbed
Divertor research program : advanced plasma image diagnostics for divertor physics
Advanced current drive research program (high field side LH, Helicon, and others)■ Easy Access of Experimental Data••
22

Direct access and faster network environment (Firewall Problem, Hadoop System)
Standardization of experimental data (MDS+  HDF5)
TOFE 2016 [Philadelphia, 2016/08/22-25]

Long-term operation and upgrade plan of KSTAR
Phase I (FY08 ~ FY12)

Phase II (FY13 ~ FY17)

Phase III (FY18 ~ FY22)

Phase IV (FY23 ~ )Superconducting
Tokamak operation

Long-pulse H-mode
and ITER pilot

Advanced scenario related
to DEMO

Advanced Technology for
K-DEMO• Integrated control of
SC tokamak• ITER priority research(ELM, Disruption, NTM)

• Advanced operation
scenario demonstrate• First plasma• High performance
plasma study using
KSTAR intrinsic tools(intermediate heating
power, low density)• Integrated control ofprofile and stability• Stabilization andoptimization ofadvanced scenario• H-mode discharge• Experimental
collaboration• Research application to
K-DEMO• Technologies at
extremeenvironments

 Targeted operation parameters• Ip ~ 2 MA, tH-mode ~ 300 s, N : ~ 5, q95 : 2 ~ 6

 System upgrade for advanced steady-state operation• NBI ~ 12 MW (Co- : 8 MW, Counter- : 4 MW)• ECH/CD ~ 6 MW, LHCD ~ 4 MW, Helicon CD ~ 4 MW
• Active cooling Divertor/PFC• Advanced divertor configuration and material R&D• Density control : pellet & cryopump• 3D field research using IVCC
23

TOFE 2016 [Philadelphia, 2016/08/22-25]

Preliminary design of off-axis NBI

ITER Project : In-kind Contribution of Korea
1. TF Conductor (Completed)

11. Test Blanket Module*

4. Thermal Shield

Total Value (kIUA) : 215.01

KO Contribution :Total Value(kIUA) : 26.88

KO Allocation : 20.2%

HCCR TBS (TBM System)

KO Allocation : 100%

KO Contribution (kIUA) : 43.39

kIUA Value : N/A

KO Contribution(kIUA) : 26.88

2. Vacuum Vessel Main Body

5. Blanket Shield Block

Total Value(kIUA) : 123.04

Total Value(kIUA) : 56.34

KO Allocation : 21.3%

KO Allocation : 49.8%

KO Contribution (kIUA) : 26.20

KO Contribution(kIUA): 28.07

3. Vacuum Vessel Port

6. Assembly Tooling

Total Value(kIUA) : 76.96

Total Value(kIUA) : 23.01

KO Allocation : 72.7%

KO Allocation : 100%

KO Contribution (kIUA) : 55.98

KO Contribution(kIUA): 23.01

7. Tritium SDS

8. AC/DC Converters

9. IVC Bus bars

10. Diagnostics

Total Value(kIUA) : 15.21

Total Value(kIUA) : 123.58

Total Value(kIUA) : 3.98

Total Value(kIUA) : 142.09

KO Allocation : 82.1%

KO Allocation : 37.3%

KO Allocation : 100%

KO Allocation : 3.2%

KO Contribution(kIUA) : 12.48

KO Contribution(kIUA): 46.06

KO Contribution(kIUA) : 3.98

KO Contribution (kIUA) : 4.49

* TBMA (TBM Agreement) was signed in 2014
Total Value : 270.54 kIUA
24

Leading Items

242016/08/22-25]
TOFE 2016 [Philadelphia,

Tokamak Main

AncillaryProcurement Schedule of the KODA

25252016/08/22-25]
TOFE 2016 [Philadelphia,

ITER Procurement Activities of Korea

26262016/08/22-25]
TOFE 2016 [Philadelphia,

Fusion Energy Development
Roadmap in Korea

27

TOFE 2016 [Philadelphia, 2016/08/22-25]

Fusion Energy Development Promotion Law
 To establish a long-term and sustainable legal framework forfusion energy development phases.

 To promote industries and institutes participating fusion energy

development by support and benefit.

 The first country in the world that prepared a legal foundation infusion 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.

28

3 : Fusion Energy Development Promotion Law
4 : Ratification of ITER Implementation Agreement
8 : Framework Plan of Fusion Energy Development(First 5-Year National Plan)
1 : The 2nd 5-year National Plan has started.

TOFE 2016 [Philadelphia, 2016/08/22-25]

Vision and Goal of Fusion Energy Development Policy
VisionPhase

Phase 1 (’07~’11)

Phase 2 (’12~’21)

Phase 3 (’22~’36)

Policy Goal

Establishment of a foundation
for fusion energy development

Development of CoreTechnology for DEMO

Construction of DEMO byacquiring construction capabilityof fusion power plants

 Acquisition of operating technology
for the KSTAR

 High-performance plasma operationin KSTAR for preparations for the
ITER Operation

Basic
Directions

Basic
Promotion
Plan

29

Secure sustainable new energy source by technological development
and the commercialization of fusion energy Participation in the international joint
construction of ITER
 Establishment of a system for thedevelopment of fusion reactor
engineering technology

Basic Promotion Plan 1 (’07~‘11) Completion of ITER andacquisition of core technology

 Development of core technology forthe design of DEMO
Basic Promotion
Plan 2 (‘12~‘16)

Basic Promotion
Plan 3 (‘17~‘21) DEMO design, construction, anddemonstration of electricity production
 Undertaking of a key role in ITER
operations
 Completion of reactor core and systemdesign of the fusion power reactor
 Commercialization of fusion technology
Basicpromotionplan 4(‘22~‘26)

Basic
promotionplan 5(‘27~‘31)

Basic
promotionplan 6(‘32~‘36)

Policy Goal
for Plan-2

R&D for DEMO Technology based on KSTAR and ITER

Primary
Strategy for
Plan-2

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
TOFE 2016 [Philadelphia, 2016/08/22-25]

DEMO Core Technology
Development Plan

30

TOFE 2016 [Philadelphia, 2016/08/22-25]

K-DEMO Core Technology Development Plan
Development of Core Technology
 3 Major Research Fields, 7 Core Technologies, 18 Detail Technologies
and 6 Major Research Facilities Through the complete technical planning process with the full participation of experts
from all fields covering fusion, fission, physics, computing, mechanics, material,
electrics, electronics, and so on.
K-DEMO 3 Major
Research Fields

K-DEMO
7 Core Technologies

Major Research Facilities

Tokamak Core Plasma Technology

Design Basis Technology

Reactor System Integration Technology• Extreme Scale Simulation Center

Safety and Licensing Technology
Material Basis Technology
Machine andSystem Engineering
Basis Technology
31

Fusion Materials Technology
SC Magnet Technology
H&CD and Diagnostics Technology
Heat Retrieval System Technology• Fusion Materials Development Center• Fusion Neutron Irradiation Test Facility• SC Conductor Test Facility• Blanket Test Facility• PMI Test Facility

TOFE 2016 [Philadelphia, 2016/08/22-25]

Major Facilities for DEMO R&D■ High-field Superconducting Magnet Development Center


SUCCEX (SUperConducting Conductor EXperiment) Facility
High-temperature superconducting magnet development■ Fusion Material R&D CenterFusion Material Test Facilities
Blanket/FW/Divertor Material Development
Neutron Irradiation Material Test Facility■ Fusion System Engineering R&D CenterFusion Nuclear Test Facilities (Thermo-hydraulics, tritium, etc.)
PMI Test Facility
Tokamak Components Development (Heating and current drive, diagnostics, etc.)■ Large-scale Simulation (Computational) Center System codes, Simulator
 Blanket design Power plant system design etc.

32

TOFE 2016 [Philadelphia, 2016/08/22-25]

Nation-wide DEMO R&D Center Planning

연구부
지
(고자기
장센터
후보지)

Daegu ProvinceBusan Province
Chonbuk Province

Extreme Environment Material R&D Hub- Fusion Reactor Materials R&D
Advanced Magnetic Field Center- Superconductor Test Facility (SUCCEX)High Enthalpy Plasma Application R&D Center- Plasma-Material Interaction Test Facility etc.
33

TOFE 2016 [Philadelphia, 2016/08/22-25]

PMI Test Facility (Chonbuk Province)● 2.4 MW High-Temperature Plasma Test Facility- Upgrade Plasma Facility for PMI Test
- Additional, Blanket Test Facility
MAGNUM-PSI (Cf.)
34

TOFE 2016 [Philadelphia, 2016/08/22-25]

Superconducting Conductor Test (SUCCEX) Facility■ SUCCEX (SUperConducting Conductor EXperiment)• Background field : 16 Tesla••

Split-pair Solenoid Magnet System
Inner-bore Size : ~ 1 m• Two Test Modes : Sultan-like sample test mode
 Semi-circle type conductor sample test mode(Cf.) SULTAN• Background field : 11 Tesla• 100 kA SC Transformer
for the short sample test

35

TOFE 2016 [Philadelphia, 2016/08/22-25]

SULTAN-type Semi-circle-type

KOMAC Site (Gyeong-ju)

KTX Station
To Seoul ~2 Hour

KOMAC Phase-2 Site
650m(L) X 400m(W)

KOMAC Site
450m(L) X 400m(W)Seoul-Busan
Expressway

36

TOFE 2016 [Philadelphia, 2016/08/22-25]

20 & 100 MeV KOMAC Proton Linac
Features of 100 MeV linac
50 keV Injector (Ion source + LEBT)
3 MeV RFQ (4-vane type)
20 & 100 MeV DTL
RF Frequency: 350 MHz
Beam Extractions @ 20 or 100 MeV
5 Beamlines for 20 MeV & 100 MeVSRF TB

RI

Neutron
Irradiation
Test Lab. Basic Science37

20 MeV DTL

100 MeV DTL

NeutronSourceAerospaceApp.

Energy (MeV)
20
Peak Current (mA)
0.1 ~ 20
Max. Duty (%)
24*
Max. Ave. Current (mA)
4.8
Pulse Width (ms)0.05 ~ 2Max. Repetition Rate120
(Hz)Max. Beam Power (kW)96
Emittance (mm-mrad) 0.22(x),0.25(y)Medical App.
NuclearMaterials

100 MeV
Beamlines

RI

Semiconduct
or

Basic
Science

LifeMedical
App.
Materials

20 MeV
Beamlines
TOFE 2016 [Philadelphia, 2016/08/22-25]

50 keV Injector
3 MeV RFQ

100
0.1 ~ 208
1.6
0.05 ~ 1.33
60
160
0.3 / 0.3

Neutron Energy Spectrum in KOMAC
Fusion Neutron similar Spectrum by Pulse-type Proton beam on Be-target (>1dpa/y)(Ref.) Institute for Materials Research, KIT
I A. Moslang

38

Neutron Energy Spectrum in KOMAC

TOFE 2016 [Philadelphia, 2016/08/22-25]

K-DEMO Plant Construction Model

39
39

TOFE 2016 [Philadelphia, 2016/08/22-25]

K-DEMO Conceptual
Design Activity

40

TOFE 2016 [Philadelphia, 2016/08/22-25]

Mission & Strategy
 Mission: To demonstrate the sustainable generation of electricity fromfusion power Strategy: Natural Path: KSTAR  ITER  DEMO (tokamak) To mitigate risks in the course of DEMO development  Two-Phased Operation
strategy The operation Stage I  not considered as a final DEMO
• At least one port will be designated for the
CTF including blanket test facility.
• To demonstrate the net electricity
generation (Qeng > 1) and the self-sufficient
Tritium cycle (TBR > 1.05).
 The operation Stage II• Major upgrade of In-Vessel-Components• To demonstrate the net electricity
generation > 400 Mwe.
• To demonstrate the competitiveness in COE.
41

TOFE 2016 [Philadelphia, 2016/08/22-25]

Key Idea of K-DEMO Design■ Current Drive and Magnetic Field
 Considering the size, a steady state Tokamak is selected as a K-DEMO.
 Because of high neutron irradiation on ion sources, NBI is not practical for the main
off-axis current drive of K-DEMO.
 Because of high density of K-DEMO plasma, high frequency ECCD systems (> 240
GHz) are required in order to minimize the deflection of wave.
 In order to match with the high frequency ECCD, a high toroidal magnetic field
Tokamak is required and the magnetic field at plasma center requires > 6.5 T.
 Also, Ip,limit ∝ B, ne, limit ∝ B, and Power ∝ R3B4 [Reactor Cost ∝ R3B2]■ Choice of Coolant and Blanket System
 Pressurized water (superheated water) is considered as a main coolant of K-DEMO
considering BOP(Balance of Plant).
 Supercritical CO2 is also considered as a future coolant.
 Helium is also a candidate as a coolant of K-DEMO, but there are concerns about its
low heat capacity, a required high pumping power and BOP.
 Both of ceramic and liquid metal blanket system is considered at this stage. But
even in the liquid blanket system, the liquid metal will not be used as a main
coolant and a water cooling system will be installed inside the liquid metal blanket.
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TOFE 2016 [Philadelphia, 2016/08/22-25]

K-DEMO Parameters■ Main Parameters
•
•
•
•
•
•
•
•

R = 6.8 m
a = 2.1 m
B-center = 7.0~7.4 T
B-peak = 16 T
95 = 1.8
 = 0.625
Plasma Current > 12 MA
Te > 20 keV■ Other Feature
•
•
•
•
•
•
43

Double Null Configuration
Vertical MaintenanceTotal H&CD Power = 80~120 MW
P-fusion = 2200~3000 MWthP-net > 400 MWe at Stage II
Number of Coils : 16 TF, 8 CS, 12 PF
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Magnet System (1/2)

 16 TF coils, PF coils – 6 upper, 6 lower. 8 CS modules

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R = 6.8 m
a = 2.1 m
x = 2.0
x = 0.625
BT = 7.4 T
Ip = 12 MA
li(1) = 0.684
li(3) = 0.52
RX = 5.48
ZX = 4.20

Magnet System (2/2)■ Electromagnetic Analyses■ TF Winding & Structure■ TF / PF / CS CICCs

TF Coil :Dual winding packs with 2 types of CICC
→ High magnetic fieldwith huge Cost savings(Strands & No Radial Plate)
Small & Large TF CICC (spiral)
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TOFE 2016 [Philadelphia, 2016/08/22-25]

PF CICC CS CICC

CICC Parameter
Parameter■ Cable pattern
No. of SC strands
No. of Copper strands
Spiral Dimension (mm)■ Void Fraction (%)■ Strand TypeTF HF(3SC)x4x5x6x5 +2 Helical Spirals
1800
ID 5 / OD 8

29.8

CS

TF LF

(((2SC+2Cu)x5)x6+7 (2SC+1Cu) x3x4x4x6
No Cooling SpiralCu)x6 + Central Spiral
576
360
288
432
ID 7 / OD 9

32.5

ITER type (Jc ~ 1000 A/mm2) Nb3Sn Strand
0.82 mm diameter(~450 ton + ~280 ton)(~102 ton + ~90 ton)

NbTi Strand
0.82 mmdiameter(~90 ton)

1.0
1.6 mm (including Voltage Tap)

■ Jacket Thickness■ Wrapping Tape
Sub-cable wrap thickness
Sub-cable wrap width
Cable wrap thickness
Final wrap width

480
240
ID 7 / OD 9High Jc (> 2600 A/mm2) Nb3Sn Strand
0.82 mm diameter(0.1 mm Kapton 400% + 0.3 mm S glass 400%)■ Twist Pitch (mm)
1st stage
2nd stage
3rd stage
4th stage
5th stage

PF5-6(2SC+1Cu)x3x4x4x5+Central Spiral

36.6

26.0

■ Cu/non-Cu of Strand■ Insulation

PF1-4

2.0 mm (including Voltage Tap)
(0.1 mm Kapton 400% + 0.4 mm S glass 400%)
5.0 mm80 ± 5140 ± 10190 ± 10245 ± 15415 ± 2080 ± 5140 ± 10190 ± 10300 ± 15-27 ± 545 ± 1085 ± 10150 ± 15385 ± 200.08 mm, 40% coverage
15 mm
0.4 mm, 60% coverage
7 mm
TOFE 2016 [Philadelphia, 2016/08/22-25]

35 ± 575 ± 10135 ± 10285 ± 15410 ± 20

Vertical Maintenance Concept■ Vertical maintenance scheme of in-vessel components

 For maintenance, in-vessel components are toroidally subdivided into: Blanket: - 16 inboard sectors- 32 outboard sectors
 Divertor: 32 modules (upper & lower each) Sectors / modules are removed through the enlarged top vertical
ports of vacuum vessel.
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Concept of Blanket
 Layered Structure of Blanket & Shielding: Solid ceramic pebble type – breeders (Li4SiO4) and multipliers (Be12Ti)
 Shielding: B4C, Borated-SS, CW, ..
 Structural material: RAFM with water-cooling■ Neutronics Analyses
Breeder Pebble

Multiplier Pebble

Li4SiO4

Be (*safety)

Li4SiO4

Be12Ti

Li4SiO4 + Be12Ti (Mixed pebbles)48

Global TBR> 1.20< 1.00 (so far)
~ 1.02 (so far)

TOFE 2016 [Philadelphia, 2016/08/22-25]

Concept of Divertor■ Tungsten mono-block type target, with RAFM cooling tube, high pressure water-cooling
InboardTargetOutboard
TargetCentralDome

OutletInlet< Thermo-hydraulic Analysis for Outboard Divertor Target >Monoblock

Details of High Heat Flux Unit
49

Tungsten mono-block
Vanadium interlayer
RAFM Cooling tube
• Coolant – PWR-like(inlet 290 oC,
T = ~ 40 oC)

W

RAFM Tube
Support

Backplate Thermal load
- 10 MW/m2
 Mechanical loads:- Water Pres. (15 MPa)
- EM load (10 kN)
Material

Calculated[ MPa]

3Sm[ MPa]

W

696

1800

RAFM

497

500

< Thermo-mechanical Analysis for a Monoblock w/ Support>

TOFE 2016 [Philadelphia, 2016/08/22-25]

Conclusion
KSTAR : Physics Machine

ITER : Fusion Engineering· High Performance (βN > 4) Plasma· Stable (βN ~ 2) Burning Plasma &Research for Fusion Power Plant

Fusion Nuclear Science Research· Fusion Physics Validation(14 MeV Neutron Effect)· Tokamak Simulator Development· Confirmation of Engineering· Design Requirement for Fusion Plant

Feasibility for Fusion Power Plant

Construction & Operation of
Artificial SUN(=Fusion Power Plant)[βN > 4 required]
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TOFE 2016 [Philadelphia, 2016/08/22-25]