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Status of KSTAR Project and Fusion Research in Korea StatusStatus ofof thethe KSTARKSTAR ProjectProject andand FusionFusion ResearchResearch inin KoreaKorea GyuGyunngg--SuSu LeeLee National Fusion R & D Center Korea Basic Science Institute Fusion Research Activities and Plan in Korea Basic Plasma and Fusion Research at University : 1970’s Construction of Small-scale Fusion Research Device : 1980-1990’s - SNUT- 79 Tokamak (SNU) - KT- 1 Tokamak (KAERI) - KAIST Tokamak (KAIST) - HANBIT Mirror Device (KBSI) Korean National Fusion Program : 1995 ∼ - KSTAR Tokamak Project : Universities, Research Institutes and Major Industries with Emphasis on International Collaboration Collaboration with Major International Fusion Program : 2005 ∼ - Operate KSTAR as International Fusion Collaboratory - Participate Major International Fusion Research Program Fusion Research at SNU SNUT-79 Tokamak Experiment Superconducting CS Model Coil Small AC Spherical Torus Experiment KT-l Tokamak (KAERI) RF Heating Physics KAERI KAIST Tokamak Diagnostics and Heating HANBIT Plasma Research Facility (KBSI) Basic Plasma Research, Diagnostic and Heating Korean National Fusion Program Time Window 1990 1995 2000 2005 2010 2015 2020 2025 2030 … JET JT-60U DIII-D Construction … Operation ASDEX-U Tore Supra … LHD … W7-X Time Window … KSTAR … ITER DEMO(?) Fusion Research and Development Strategy FusionFusion EnergyEnergy ITERITER (( International Plan )) KSTARKSTAR (( Na tiona l Pla n )) Institutional Programs Korean National Fusion R&D Plan 1995 Year World-wide Tokamak Performance and KSTAR Target DEMO 9 ITER 10 Projected (World-Wide) 108 Achieved (World-Wide) JET Output TFTR 7 r Projected (Korea) e) 10 l e JT-60U a Achieved (Korea) KSTAR w 6 c 10 JET S (300 S) Po 5 g 10 TFTR JET/TFTR o on 4 DIII-D i L 10 s u in 3 s PDX F 10 t DIII att 102 PLT len (W a v 101 ALCATOR A ALCATOR C 1 ATC KAIST-T Equi SNUT-79 10-1 KT-1 10-2 1970 1975 1980 1985 1990 1995 2000 2005 2010 Year Program and Project Management Structure NationalNational Fusion Fusion Council Council SteeringSteering Com Commmitteeittee NationalNational Fusion Fusion R&D R&D Center Center PrincipalPrincipal Investigator Investigator Co-InvestigatorCo-Investigator Com Commmitteeittee ProjectProject Control Control & & PPrrojectoject Engin Engineereeringing PPrrojectoject P Phhyyssicicss ( S(Science)cience) FaciliFacilityty Constru Construcctiontion AdmAdministrationinistration SySysstetemmss SubsySubsysstetem/m/ SubsySubsysstetem/m/ IndustrIndustryy InternationalInternational EngineerEngineeringing InstituteInstitute UniversityUniversity KSTAR Machine Parameters Parameters Remarks Major Radius, R0 1.8 meter Minor Radius, a 0.5 meter • Toroidal Field, BT0 3.5 Tesla Nb3Sn, NbTi Plasma Current, IP 2.0 MA Elongation, κ 2.0 Triangularity, δ 0.8 • Double-null • Pulse Length 20 sec < t pulse < 300 sec Current Drive Heating & Current Drive NBI, ICRH / FWCD LHCD, ECH / ECCD Plasma Species H/D KSTAR Tokamak Start Date 951228 Data Date 010531 KSTAR SUMMARY SCHEDULE [Update 3D] Milestone PHASE I PHASE II PHASE III Commissioning KSTAR Project CR DPD PVR TSER ASER FCS FER BO Assembly 1st Start Finish Plasma Facility Design Basic Facility Construction Facility Construction Research Building Special Facility Engineering Design Special Facility Construction Concept Conceptual Basic Main Tokamak System Definition Design Design Tokamak Systems R&D Engineering Design - Vacuum Vessel / Cryostat Final Design & Preproduction Test & Support Structure - PFC / In-Vessel Coils Fab. VV Fab. Cryostat / Support Structure Fabricate PFC / Others Fab. Inboard Limiter - Superconducting Magnets Engineering Design 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 R&D Engineering Design Ancillary Systems Final Design - Aux. Heating Sys - Vacuum Pumping Sys - Power Supply Sys - Diagnostic Sys Fab. PF-5U PS Fab. TF PS Fab. PF-1,3UL PS Fab. PF-2,7 PS Fab. PF-4UL, 5L, 6UL PS - Control & Data Sys Deliver ECH Deliver ECH Install Fabricate Baseline Ancillary Systems Prepare Area Local I&C Basic Diag. Assembly & Operation & Assembly Tooling Assemble & Install Lower TF/VV Upper Ports / Others Integrated PF PF/CS Sys Test First Plasma KSTAR Tokamak System Engineering : Under Eng. Design : Prototype Fabrication : Eng. Design Completion : Under Construction KSTAR Tokamak Layout KSTAR OPERATION SCHEDULE [ Update 2 ] Milestone Initial Operation Baseline Operation Upgrade Advanced Operation Assembly First Baseline Upgrade Upgrade Long-pulse Integrated AT AT Reactor Finish Plasma Start Finish Operation Operation 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 (1.5 T) (3.5 T) Operation Warm-up Physics Objectives Circular Shaped OH 20s NBI NBI Full Scope 20s ECH/ECCD Long-pulse 300s 300s Full Scope Ohmic Short-pulse ICRH/FWCD ICRH/FWCD Experiment Neo-TM Experiment High Integrated 300s NBI Divertor-I LHCD Divertor-II Performance AT Experiment Experiment FEC/RWM Experiment Vent Period 1st Break 2nd Break 3rd Break 4th Break 5th Break 6th Break 7th Break 8th Break 9th Break Installation & Upgrade Install Install Install Install Inboard Limiter PFC Pellet Injector PFC Upgrade In-vessel Components, Power Supply & Others Install Install Install IC Coil P.S. FEC/RWM Coil P.S. P.S. Upgrade Install Install Install Install Install Install Install Install ECH NBI-1(8MW) ICRH/FWCD (6MW) LHCD (1.5MW) NBI-2 (8MW) ECH/ECCD (1MW) FWCD&LHCD Upgrade ECH/ECCD Upgrade (3MW) Heating & Current Drive ECH/ECCD FWCD&LHCD ECH/ECCD Decision Upgrade Upgrade Decision Install Decision Basic Diagonostics Diagnostics & Control Install Install Install Implement Install Install Install Implement Baseline I Diag. Baseline II Diag. Baseline III Diag. Integrated Advanced I Diag. Advanced II Diag. Advanced III Diag. AT Simulator Control Facility Construction Baseline Utility Installation PFC Cooling Power System Upgrade 154kV MG Installation Cryo System Upgrade D-D Shielding Installation & Commissioning Cooling System Upgrade KSTAR Experimental Building KSTAR Facility Construction Status November 2001 Diagnostics Development (KBSI, KAERI, KAIST, Univ.) Heating System Development (KAERI, POSTech) RF Heating System MW System NBI Heating System KAERI KSTAR SC Magnet Facility (Samsung) KSTAR SC Magnet Fabrication KSTAR Vacuum Vessel Fabrication (HYUNDAI) KSTAR Vacuum Vessel Test KSTAR Power Supply Fabrication (POSCON) 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” !! International Collaboration Governments : - U.S. - Korea Cooperation Agreement in the Area of Fusion Energy Research & Related Fields, June, 1996. 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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