Gyung-Su Lee National Fusion R & D Center Korea Basic Science Institute

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1 Status of the KSTAR Project and Fusion Research in Korea Gyung-Su Lee National Fusion R & D Center Korea Basic Science Institute

2 Fusion Research Activities and Plan in Korea Basic Plasma and Fusion Research at University : 1970 s Construction of Small-scale Fusion Research Device : s - SNUT- 79 Tokamak (SNU) - KT- 1 Tokamak (KAERI) - KAIST Tokamak (KAIST) - HANBIT Mirror Device (KBSI) Korean National Fusion Program : KSTAR Tokamak Project : Universities, Research Institutes and Major Industries with Emphasis on International Collaboration Collaboration with Major International Fusion Program : Operate KSTAR as International Fusion Collaboratory - Participate Major International Fusion Research Program

3 Small AC Spherical Torus Experiment Fusion Research at SNU SNUT-79 Tokamak Experiment Superconducting CS Model Coil

4 KT-l Tokamak KAERI RF Heating Physics KAERI

5 KAIST Tokamak Diagnostics and Heating

6 HANBIT Plasma Research Facility KBSI Basic Plasma Research, Diagnostic and Heating

7 Korean National Fusion Program Time Window JET JT-60U DIII-D ASDEX-U Tore Supra Construction LHD Operation Time Window W7-X KSTAR DEMO(?) ITER

8 Fusion Research and Development Strategy Fusion Energy ITER International Plan KSTAR National Plan Institutional Programs Korean National Fusion R&D Plan 1995 Year

9 World-wide Tokamak Performance and KSTAR Target Equivalent Fusion Power Output (Watts in Log Scale) Projected (World-Wide) Achieved (World-Wide) Projected (Korea) Achieved (Korea) PLT PDX TFTR DIII ALCATOR A ALCATOR C ATC SNUT-79 TFTR JET JET/TFTR DIII-D Year JET JT-60U KAIST-T KT-1 ITER KSTAR DEMO

10 Program and Project Management Structure National Fusion Fusion Council Council National Fusion Fusion R&D R&D Center Center Principal Investigator Steering Committee Co-Investigator Committee Project Project Engineering Project Project Physics Physics (Science) Facility Facility Construction Project Project Control Control & Administration Systems Engineering Subsystem/ Institute Institute Subsystem/ University Industry Industry International

11 KSTAR Machine Parameters Major Radius, R 0 Minor Radius, a Toroidal Field, B T0 Plasma Current, I P Elongation, κ Triangularity, δ Parameters 1.8 meter 0.5 meter 3.5 Tesla 2.0 MA Remarks Nb 3 Sn, NbTi Double-null Pulse Length Heating & Current Drive Plasma Species 20 sec < t pulse < 300 sec NBI, ICRH / FWCD LHCD, ECH / ECCD H/D Current Drive

12 KSTAR Tokamak

13 Start Date Data Date KSTAR SUMMARY SCHEDULE [Update 3D] Milestone PHASE I PHASE II PHASE III Commissioning KSTAR Project Start CR DPD PVR TSER ASER FCS FER BO Assembly Finish 1st Plasma Facility Construction Facility Design Research Building Basic Facility Construction Special Facility Engineering Design Special Facility Construction Main Tokamak System Concept Definition Conceptual Design Basic Design Tokamak Systems R&D Engineering Design - Vacuum Vessel / Cryostat & Support Structure Final Design & Preproduction Test - PFC / In-Vessel Coils - Superconducting Magnets Engineering Design Fab. VV Fab. Cryostat / Support Structure Fab. Inboard Limiter Fabricate PFC / Others Final Design Fabricate Conductor NbTi 12T Fabricate T.F.S.C.M. Nb3Sn 8T Nb3Sn 7T Nb3Sn 8T Nb3Sn 4T TF 00 TF1-6 TF7-10 TF11-16 Fabricate P.F.S.C.M. BKG PF6-7 PF5 PF1-4 Ancillary Systems Assembly & Operation Ancillary Systems R&D - Aux. Heating Sys - Vacuum Pumping Sys - Power Supply Sys - Diagnostic Sys - Control & Data Sys Engineering Design Prepare Area & Assembly Tooling Final Design Fab. PF-5U PS Fab. TF PS Fab. PF-1,3UL PS Fab. PF-2,7 PS Fab. PF-4UL, 5L, 6UL PS Deliver ECH Assemble & Lower PF Deliver ECH Local I&C TF/VV Upper PF/CS Basic Diag. Ports / Others Fabricate Baseline Ancillary Systems Integrated Sys Test First Plasma

14 KSTAR Tokamak System Engineering : Under Eng. Design : Prototype Fabrication : Eng. Design Completion : Under Construction

15 KSTAR Tokamak Layout

16 KSTAR OPERATION SCHEDULE [ Update 2 ] Milestone Initial Operation Baseline Operation Upgrade Advanced Operation Assembly Finish First Plasma Baseline Upgrade Start Upgrade Finish Long-pulse Operation Integrated AT Operation AT Reactor Prototype Operation Campaign Commissioning 1st Campaign 2nd Campaign 3rd Campaign 4th Campaign 5th Campaign 6th Campaign 7th Campaign 8th Campaign 9th Campaign 10th Campaign Cooldown & Leak Check Magnet Test & Field Mapping Operation Warm-up Physics Objectives (1.5 T) Circular Ohmic (3.5 T) Shaped OH Short-pulse NBI 20s NBI ICRH/FWCD Divertor-I FEC/RWM NBI ICRH/FWCD LHCD Full Scope 20s Experiment ECH/ECCD Neo-TM Long-pulse Experiment Divertor-II 300s High Performance Experiment 300s Integrated AT Experiment Full Scope 300s Experiment Vent Period 1st Break 2nd Break 3rd Break 4th Break 5th Break 7th Break 8th Break 9th Break 6th Break ation & Upgrade In-vessel Components, Power Supply & Others Inboard Limiter IC Coil P.S. PFC FEC/RWM Coil P.S. Pellet Injector PFC Upgrade P.S. Upgrade Heating & Current Drive Diagnostics & Control Facility Construction ECH NBI-1(8MW) Basic Diagonostics Baseline I Diag. Baseline Utility ation 154kV ation ICRH/FWCD (6MW) LHCD (1.5MW) Baseline II Diag. MG ation & Commissioning PFC Cooling ECH/ECCD Decision Baseline III Diag. D-D Shielding NBI-2 (8MW) FWCD&LHCD Upgrade Decision Implement Integrated Control ECH/ECCD (1MW) FWCD&LHCD Upgrade Advanced I Diag. ECH/ECCD Upgrade Decision Power System Upgrade Cryo System Upgrade Cooling System Upgrade ECH/ECCD Upgrade (3MW) Implement Advanced II Diag. Advanced III Diag. AT Simulator

17 KSTAR Experimental Building

18 KSTAR Facility Construction Status November 2001

19 Diagnostics Development KBSI, KAERI, KAIST, Univ.

20 Heating System Development KAERI, POSTech RF Heating System KAERI NBI Heating System MW System

21 KSTAR SC Magnet Facility Samsung

22 KSTAR SC Magnet Fabrication

23 KSTAR Vacuum Vessel Fabrication HYUNDAI

24 KSTAR Vacuum Vessel Test

25 KSTAR Power Supply Fabrication POSCON

26 KSTAR Project Role in World-wide Fusion Research The KSTAR project will make critical contributions to the world fusion research and development program. It will: Extend advanced tokamak research to high performance and steady state operation regimes. Contribute techniques for successful steady state physics operation. Compare advanced tokamak physics results with those from superconducting stellarators and spherical tokamaks. Utilize KSTAR as International Fusion Collaboratory!!

27 International Collaboration Governments : - U.S. - Korea Cooperation Agreement in the Area of Fusion Energy Research & Related Fields, June, Institutions : - Princeton Plasma Physics Laboratory, U.S.A. - Plasma Science & Fusion Center, M.I.T., U.S.A. - National Institute for Fusion Science, Japan - Max-Planck Institute for Plasma Physics, Germany - UKAEA Fusion Culham, U.K. - CEA Cadarache, France - Kurchatov Institute, Russia - Efremov Institute, Russia - Institute of Plasma Physics, Academy of Sciences, China - South West Institute of Physics, China International Energy Agency: Implementing Agreement

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