KSTAR, ITER and K-DEMO

Introduction of Korean Fusion Program : KSTAR, ITER and K-DEMO

Si-Woo Yoon National Fusion Research Institute, Daejeon, Korea

Global Research Platform Workshop 2019 Atkinson Hall, San Diego, 17-18 SEP 2019

National Research Council of National Fusion Ministry of Science and ICT Science & Technology Research Institute Contents

- Introduction to KSTAR program (application of vacuum tubes to KSTAR) - Introduction to ITER project - Strategy for DEMO (V-DEMO and Fusion Loadmap) Overview of Fusion R&D - Fusion Energy 3

1H 1H 2H  β   ν 1.2 MeV 1H 2H 3He    5.5 MeV 3He3He4He 21H 12.9 MeV

• Fusion energy (nuclear fusion) .. The source of energy that the sun and stars emit for 10 billion years • The most natural and universal energy source - Steady, Unlimited, and Natural Energy Overview of Fusion R&D – Realization of Artificial Sun on Earth 4

 Representative fusion reaction

Deuterium (D) Neutron (n): 14.1 MeV

17.6 MeV

Tritium (T) Helium (He): 3.5 MeV

 Essential tasks for commercialization of nuclear fusion

1. High-temperature plasma 2. Fusion thermal output 3. Extreme materials and power containment : D-T fusion reaction conversion : High-performance plasma heating :  -particle (4He) confinement : Neutron energy conversion (blanket) : Long-time operation control : ITER Core Technology Research : Self sufficiency of tritium fuel : KSTAR Core Technology Research : DEMO Core Technology Research

Outboard Inlet Inboard Target Outlet Target Central Dome

Cassette Body 3a. KSTAR (Korea Superconducting Tokamak Advanced Research) 5

• Secure the technology for construction and operation of superconducting fusion device • Lead the research for long-time operation of high-performance plasma and secure the core technology for fusion reactor

KSTAR superconducting fusion device High frequency Neutral particle beam heating device heating device (RF & microwave) (NBI-1 heating)

Plasma diagnostics device (Diagnostics)

Expansion of heating device underway (NBI-2 upgrading) Inside of vacuum vessel and plasma World-wide Fusion Research Program 6 Global Fusion Trends and Korea's Overview of Fusion R&D - 7 Mid-Entry Strategy

 Changes in fusion paradigm: . Pulse type  Long-time operation using superconducting magnet . West-centered (US, Europe)  Asia-centered (Korea, China, Japan)

Conventional Device (Cu) Enactment of Fusion Energy Development Promotion Act DEMO (2006) ITER Superconducting Device Establishment of Fusion Energy Development Basic Promotion Plan (2007) 1GW JET FIRST MOVER TFTR KSTAR JT-60U 1MW

JET EAST TFTR JET / TFTR

FAST FOLLOWER 1KW DIII-D PDX DIII

Fusion Fusion Power PLT ALCATOR C Superconducting Device 1W T-3 KAIST-T (1968) ATC ALCATORE SNUT-79 KT-1

1965 1970 1975 1980 1985 1990 1995 2000 2005 2010 2020 2030 2040 Establishment of National FusionYear Research & Development Basic Plan, Start of KSTAR Project (1995) KSTAR mission is 8 to explore the steady-state operation at high performance

 Key parameters of KSTAR, ITER & K-DEMO ▶ Operation goals KSTAR ITER K-DEMO Parameters • to achieve steady state H-mode (achieved) (Baseline) (Option II)

operation with resolving engineering Major radius, R0 [m] 1.8 () 6.2 6.8 issues (ELM, disruption) and Minor radius, a [m] 0.5 () 2.0 2.1 • to explore high performance Elongation,  2.0 (2.16) 1.7 1.8 operation modes with resolving Triangularity,  0.8 () 0.33 0.63 harmful MHDs Plasma shape DN, SN SN DN (SN)

Plasma current, IP [MA] 2.0 (1.0) 15 > 12

Toroidal field, B0 [T] 3.5 () 5.3 7.4 H-mode duration [sec] 300 (70) 400 SS

N 5.0 (4.3) ~ 2.0 ~ 4.2

Bootstrap current, fbs (~0.5) ~ 0.6

Superconductor Nb3Sn, NbTi Nb3Sn, NbTi Nb3Sn, NbTi (2016) Heating /CD [MW] ~ 28 (10) ~ 73 120 PFC C, W W W

Fusion power, Pth [GW] ~0.5 ~ 3.0 How can KSTAR support ITER? 9 Exclusive uniqueness in KSTAR could make it.

▶ Better plasma symmetry ▶Better instability control with IVCC -5 • • Lowest error field (훿B/B0~1x10 ) Uniquely top/middle/bottom coils • Lowest toroidal ripple (~0.05 %) • Reliable ELM-crash suppression (>30s)

▶ Better understanding by Advanced ▶ Better efficiency in heating/CD & diagnostic ready to upgrade • Profile and 2D imaging diagnostics • Long pulse high beta op. using NBI (>70s) • Physics validation of MHD & confinement • 2nd NBI system is under construction

ECEI Image bolometer MSE

#16498 2500 ms (w/ ITB) 4500 ms (w/o ITB H-mode) 6500 ms (w/o ITB L-mode)

psi_n 3D Imaging of MHD Instabilities 10

Sawtooth Tearing mode Edge-localized modes

18.5°

. Two independent ECEI systems will be installed on the KSTAR in 2018, which is toroidally separated by 18.5 degree, to visualize the MHD and turbulence in quasi-3D for wide range of KSTAR operation. . Due to flexible optics and LO system, the view position of two ECEIs will be focused anywhere in the midplane with sufficient vertical coverage. KSTAR Project - World's Top Research Achievement 11

 Secured the core technology for fusion reactor as world leader for long-time operation of fusion plasma

. ITER operation .. High-performance plasma longest operation (over 1 minute, ’16) . ITER challenge .. Edge-Localized Mode(ELM) suppression (the longest in the world, ‘17) . Started research on operation mode for advanced fusion reactor (‘16~) . Re-analysis of plasma physical phenomena (advanced diagnostics device, simulation)

Plasma current (0.45MA) Loop voltage (~ 0.1 V)

NBI heating power (~ 4MW) ECH power (0.8 MW)

34 sec  wall

Density (2.7 x 10 19 / m 3) Temperature (3 keV)

0 10 20 30 40 50 60 70 Time (s)

Obtained long-time maintenance technology of high- Achieved suppression of plasma ELM using performance H mode (more than 1 minute) in-vessel control coil (IVCC) (~ 34 sec) Long-pulse sustainment of high performance discharge 12

 In 2015, fully non-inductive high P (>3)  In 2019, 90 s of H-mode operatio discharge was found n achieved with NBI+ECH • NBI driven fully non-inductive • βP = 3.0, βN = 2.0, • Pulse limited due to PFC overheating by excessive fast ion loss

Fully inductive, high P (> 3.0) discharge at 3.0 T Research and upgrade plan for higher beta and steady-state operation

2008 2017 Long-pulse H-mode research •Long pulse H-mode (>70s) •ELM research & control (>30s) First plasma Long-pulse H-mode •Alternative operation modes (ITB, low q, ..) (ECH 84 GHz) (NBI~5.5 MW) (ECH~1 MW)

2017 2021 Advanced scenario & MHD research • Stable high beta operation

(N >3.0, Tion ~ 10 keV) Heating upgrade • Advanced mode develop. (NBI~12 MW) (hybrid, ITB, low q) (ECH~6 MW) • MHD & disruption control

2021 2025 ~ Steady-state & reactor mode research • Tungsten divertor & active cooling (10 MW/m2) Divertor upgrade Advanced current • Advanced current drive under test (Tungsten divertor) drive (HFS LHCD & Helicon CD) (Detached divertor) (LHCD~4 MW) or • Steady-state operation (~300s) (Diagnostics) (Helicon CD~4 MW) ITER (International Thermonuclear Experimental Reactor) 14

• Final engineering demonstration for commercialization of fusion energy through international joint construction and operation efforts • Target of achieving 500MW thermal power and 10-fold energy amplification rate (Q) • 7 countries: USA, EU, Japan, Russia (Apr. '88), China (Jan. '03), Korea (Jun. '03), India (Dec. '05)

France

ITER ITER Project 15 16 ITER Research Plan (IRP) : Staged approach to DT operation

A. Loarte, ITER IO K-DEMO - Goals and Strategy 17

■ Main Parameters • R = 6.8 m / a = 2.1 m • B0 = 7.0~7.4 T / B-peak = 16 T • elongation = 1.8 • triangularity = 0.625 • Plasma current > 12 MA • Te > 20 keV

■ Other Features • Double-null & Single-null configuration • Vertical Maintenance • Total H&CD Power = 80~120 MW • P-fusion = 2200~3000 MW • P-net > 400 MWe at Stage II • Number of Coils : 16 TF, 8 CS, 12 PF KO Approach for K-DEMO Technology 18  Bridging the present (KSTAR, ITER) and the future (K-DEMO) reactors via Computer Simulation

̶ Validated simulations with data provided by KSTAR, ITER and Blanket facilities

̶ Integrated simulations of engineering components (Blanket, BOP, licensing etc)

̶ Optimization of K-DEMO simulations, Reduced risks and construction costs Virtual DEMO K-DEMO

Optimization & Reduced costs KSTAR

Basic Fusion R&D Program ITER

Blanket R&D 19 Facility Nuclear Plant • Plant BOP Simulation

Simulator • Plan Design & Safety Technology Integrated Virtual DEMO Analysis Fusion Plant  K-DEMO Design & Safety Analysis and Licensing Support Simulation

High Speed Fusion Simulation

Hi Fidelity Big Data Analysis for Experimental Data Fusion for Simulation Simulation Fusion Validation KSTAR, ITER, Blanket Experiment

20  Currently using KREONET in close collaboration with KISTI for KSTAR data sharing

 Plan to include V-DEMO and ITER in future

KSTAR ITER

Virtual DEMO

100G 10/100G 10/100G (plan)

100G 10/100G 10/100G 100G SW Science DMZ

Domestic/International Collaborators 21 Testing the Fast Data Transmission between KSTAR and PPPL with KERONET

KSTAR network configuration

Data Transmission Flow

History of Improvement Performance of KSTAR network

※If the server is in firewall system, the network bandwidth is very slow. ※We got the result of bandwidth as 3.88Gbps with tcp 25 streams by iperf between KSTAR and PPPL even though the server of PPPL was in F/W at PPPL.

In F/W at Front of F/W at PPPL(only used the Access Control PPPL List of network switch) Planning the fast data sharing architecture into the world

USA

High

(Over (Over 10Gbps)

Speed Speed Transmission

High-Speed Transmission Real Time Transmission (Over 10Gbps) (Direct Connection) (Under 10Gbps) Mirroring Data Generated Data

100Gbps(KREONET), Data Mirroring and High-Speed Transmission(Under 10Gbps) Analysis program on High-Performance Computing(GSDC) KOREA We appreciate the contribution and collaboration of the 24 international partners in Korean fusion program

EUROfusion International Collaborators DOE F4E PPPL ITER ORNL IPP General Atomics CCFE NRC, KI Columbia U. EFDA-JET JINR MIT CEA-IRFM Gycom UCSD ENEA PELIN UC Davis Wigner LBNL QST TU/e Princeton U. ASIPP NIFS York U Wisconsin U. SWIP Nagoya U. CRPP-EFPL SLAC HUST Kyusu U. KIT NCKU FNAL Politechnico du Torino IPR

ANU

EU & Russia : Asia & Australia : USA : • Heating & CD (CEA) • Heating & CD (QST) • Heating & CD (PPPL, GA, SLAC) • Diagnostics (ENEA, TU/e, Wigner) • Diagnostics (NIFS, QST, Nagoya • Diagnostics (ORNL, MIT) • PWI, fueling (ITER, PELIN) U, Kyushu U. ASIPP, HUST, ANU) • 3D physics (GA, PPPL, Columbia U) • Theory & analysis (York U) • PWI, fueling (ASIPP, SWIP) • Plasma control & CODAC (GA, • Experiments (JET, AUP, WEST) • MHD physics & simulation PPPL, ORNL, FNAL) • ELM, PSI, CODAC (ITER) (NCKU) • ETC • ETC • Joint workshop (A3 project) • ETC

Thank you for your attention !

Ministry of Science and ICT 25