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

Similar documents
2. Composing and characteristics of EAST

Korean Fusion Energy Development Strategy*

Status of the KSTAR Superconducting Magnet System Development

ICRF Physics in KSTAR Steady State

The Results of the KSTAR Superconducting Coil Test

Impact of Pohang Accelerator to Large-scale Science Programs in Korea

System Upgrades to the DIII-D Facility

TOKAMAK T-15MD: experience of scientific and technical project realization in RUSSIA

KSTAR Construction and Commissioning

Advanced Tokamak Program and Lower Hybrid Experiment. Ron Parker MIT Plasma Science and Fusion Center

US ITER Electron Cyclotron System White Paper

Design study for JT-60SA ECRF system and the latest results of JT-60U ECRF system

What does this all mean?

A Modular Commercial Tokamak Reactor with Day Long Pulses

Recent progress of 170 GHz Gyrotron in KSTAR

3.4 Poloidal Field Power Supply Systems for the EAST Steady State Superconducting Tokamak

Roadmap Panel. 11:00 13:00 Tuesday, 17 September Auditorium Palau de Congressos de Barcelona. Moderated by Mohamed Abdou

Improvements in the fast vertical control systems in KSTAR, EAST, NSTX and NSTX-U

Physics, Technologies and Status of the Wendelstein 7-X Device

A roadmap to the realization of fusion energy

A Pathway to DEMO - Activities for DEMO in Korea

Status Alcator C-Mod Engineering Systems. DoE Quarterly Review October 27, 2005

Magnets Y.C. Saxena Institute for Plasma Research. 1/16/2007 IPR Peer Review Jan

Operational progress of 170GHz 1MW ECH system in KSTAR

3.10 Lower Hybrid Current Drive (LHCD) System

Worldwide Timelines for Fusion Energy. Laila El-Guebaly 11/19/2017

Overview of ICRF Experiments on Alcator C-Mod*

Development Status of KSTAR LHCD System

Magnetics and Power System Upgrades for the Pegasus-U Experiment

2.3 PF System. WU Weiyue PF5 PF PF1

Launcher Study for KSTAR 5 GHz LHCD System*

Design of the COMPASS Upgrade Tokamak

Status and Plan for VEST

Supported by. Overview of Transient CHI Plasma Start-up in NSTX. Roger Raman University of Washington

H. Y. Lee, J. W. Lee, J. G. Jo, J. Y. Park, S. C. Kim, J. I. Wang, J. Y. Jang, S. H. Kim, Y. S. Na, Y. S. Hwang

Status of JT-60SA Project

Status of Japanese DA

Novel Vacuum Vessel & Coil System Design for the Advanced Divertor Experiment (ADX)

Statement of Bernard Bigot Director-General ITER International Fusion Energy Organization

National Fusion Research Institute a. Princeton Plasma Physics Laboratory

IAEA-CN-94/FT/2-2 Test Results on Systems Developed for SST-1 Tokamak

To reach any of these experts, please contact Larry Bernard at (609) or

Upgradation of Aditya Tokamak with Limiter Configuration to Aditya Upgrade Tokamak with Divertor Configuration

Wall Conditioning Strategy for Wendelstein7-X. H.P. Laqua, D. Hartmann, M. Otte, D. Aßmus

Contributions of Advanced Design Activities to Fusion Research

A Design Study of Stable Coil Current Control Method for Back-to-Back Thyristor Converter in JT-60SA

Technical Readiness Level For Plasma Control

Framework for a Road Map to Magnetic Fusion Energy. Status Report

HIGH-POWER CORRUGATED WAVEGUIDE COMPONENTS FOR mm-wave FUSION HEATING SYSTEMS

RF Heating and Current Drive in the JT-60U Tokamak

Implementing Agreement for Co operation in Development of the Stellarator Heliotron Concept (SH IA) Strategic Plan

The report includes materials of three papers:

Design and Construction of JT-60SA Superconducting Magnet System

Experimental results and Upgrade plan of ECH/CD system in KSTAR

Present status of the SST-1 project

DEMO work in future. Association Euratom-Tekes. Leena Aho-Mantila VTT Technical Research Centre of Finland. Euratom-TEKES Annual Seminar 2013

DEMO-EUROFusion Tokamak, Design of TF Coil Inter-layer Splice Joint

CRYOGENICS OPERATIONS 2008

Active Control for Stabilization of Neoclassical Tearing Modes

GA A25836 PRE-IONIZATION EXPERIMENTS IN THE DIII-D TOKAMAK USING X-MODE SECOND HARMONIC ELECTRON CYCLOTRON HEATING

Importance of edge physics in optimizing ICRF performance

Iran Will Contribute to the International Thermonuclear Fusion Experiment

Error Fields Expected in ITER and their Correction

Helicon Wave Current Drive in KSTAR Plasmas

Recent Activities on SST-1 and ADITYA-U Tokamaks )

High Performance Engineering

Fusion Energy Sciences Program Update

ASG presentation and activities. Roberto Penco (consultant to ASG)

Fusion Nuclear Science and T e T chnology Progr ogr m Issues and Strategy for Fusion Nuclear Science Facility (FNSF)

Overview and status of the prototype project for Wendelstein 7-X control system

A new approach to funding, accelerating, and commercializing fusion. R. Mumgaard CEO --Commonwealth Fusion Systems NAS comments, PPPL, April 12, 2018

Toroidal Rotation and Ion Temperature Validations in KSTAR Plasmas

Study of Elliptical Polarization Requirement of KSTAR 84-GHz ECH System

Foundations for Knowledge Management Practices for the Nuclear Fusion Sector

Interdependence of Magnetic Islands, Halo Current and Runaway Electrons in T-10 Tokamak

HIGH MAGNETIC FIELD SUPERCONDUCTING MAGNETS FABRICATED IN BUDKER INP FOR SR GENERATION

The use of technical readiness levels in planning the fusion energy development

Long Pulse ICRF and ECH Experiment in LHD

Development in Russia of Megawatt Power Gyrotrons for Fusion

Abstract. PEGASUS Toroidal Experiment University of Wisconsin-Madison

TOROIDAL ALFVÉN EIGENMODES

Installation of 84-GHz, 500-kW KSTAR ECH system

Engineering Aspects of Compact Stellarators *

International Journal of Advance Engineering and Research Development. Comparison between Conceptual design of Main Parameters for Small scale and

Fault Analysis of ITER Coil Power Supply System

THE CRYOGENIC SYSTEM OF TESLA

Preliminary ARIES-AT-DCLL Radial Build for ASC

3D full wave code modelling of ECRF plasma heating in tokamaks and ITER at fundamental and second harmonics

PROGRESS IN IFMIF HALF WAVE RESONATORS MANUFACTURING AND TEST PREPARATION

Abstract. *Supported by U.S. DoE grant No. DE-FG02-96ER Pegasus Toroidal Experiment University of Wisconsin-Madison

Diagnostic development to measure parallel wavenumber of lower hybrid waves on Alcator C-Mod

3.7 Grounding Design for EAST Superconducting Tokamak

Structural Analysis of High-field-Side RF antennas during a disruption on the Advanced Divertor experiment (ADX)

Whistlers, Helicons, Lower Hybrid Waves: the Physics of RF Wave Absorption for Current Drive Without Cyclotron Resonances

High Field Side Lower Hybrid Current Drive Launcher Design for DIII-D

Heating Issues. G.Granucci on behalf of the project team

First Results From the Alcator C-Mod Lower Hybrid Experiment.

Design of an ICRF Fast Matching System on Alcator C-Mod

Critical Problems in Plasma Heating/CD in large fusion devices and ITER

Lower Hybrid. Ron Parker Alcator C-Mod PAC Meeting January January 2006 Alcator C-Mod PAC Meeting 1

Transcription:

Status of the KSTAR Project and Fusion Research in Korea Gyung-Su Lee 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

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

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 ASDEX-U Tore Supra Construction LHD Operation Time Window W7-X KSTAR DEMO(?) ITER

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

World-wide Tokamak Performance and KSTAR Target Equivalent Fusion Power Output (Watts in Log Scale) 10 9 10 8 10 7 10 6 10 5 10 4 10 3 10 2 10 1 1 10-1 10-2 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 1970 1975 1980 1985 1990 1995 2000 2005 2010 Year JET JT-60U KAIST-T KT-1 ITER KSTAR DEMO

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

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 2.0 0.8 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

KSTAR Tokamak

Start Date 951228 Data Date 010531 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

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 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

KSTAR Experimental Building

KSTAR Facility Construction Status November 2001

Diagnostics Development KBSI, KAERI, KAIST, Univ.

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

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