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Gyrotron Design EC Systems Status & Prospects Presented by G.G. Denisov Institute of Applied Physics, Nizhny Novgorod, 603950, Russia Gycom Ltd, Nizhny Novgorod, 603155 Russia 4th IAEA DEMO Programme Workshop 15–18 November 2016 Karlsruhe, Germany Contributions: • M.Henderson. ITER IO • EU team (S. Garavaglia, W. Bin, A. Bruschi, G. Granucci, G.Grossetti, J.Jelonnek, A. Moro N. Rispoli D. Strauss, M.Thumm, Q.M. Tran and T. Franke, …) • R. Ikeda. QST, Naka, Japan • T. Kariya. University of Tsukuba, Japan Russian colleagues from • Institute of Applied Physics • Gycom Ltd, • Kurchatov Institute • ITER DA • RT Soft 2 OUTLINE • First steps and main events • List of running and near future EC systems • EC systems: aims and content • ITER EC system • Necessary steps from ITER to DEMO • New developments for future EC systems o Higher gyrotron frequency o Multi-frequency operation o Broad band window o Remote steering launcher Summary 3 • First steps and main events • List of running and near future EC systems • EC systems: aims and content • ITER EC system • Necessary steps from ITER to DEMO • New developments for future EC systems o Higher gyrotron frequency o Multi-frequency operation o Broad band window o Remote steering launcher 4 Some dates from “ancient” history 1964 – first experiments with gyrotrons 70s – 100 GHz/1MW/ 100 mks/ TE22.2 28 GHz/100kW/CW first use to heat plasma at TM-3, TUMAN-2 80s – 100GHz/2.1MW/10mks/coax./ 0.5 MW/sec wide use in plasma experiments Main Events 1990-2006 First depressed collectors in megawatt gyrotrons First CVD diamond gyrotron windows Demonstration of CW operation of MW power gyrotrons Remote steering antenna concept MW gyrotron complexes at major fusion installations Last decade 2007-2016 Great progress in ITER system development • Demonstrated required gyrotron parameters/Reliability tests • Manufacturing began Results on 1.5-2 MW gyrotron models Multi-frequency gyrotrons Higher frequency gyrotrons (first steps) New ideas ECW systems (examples) Running installations with ECW systems: DIII-D, FTU, TCV, JT-60U, LHD, ASDEX-Upgrade, T-10, W7-AS, … 80-170 GHz/ 2-5 MW/1-10 sec Developments for running machines: EAST 140 GHz/ 5 MW/ 1000 sec KSTAR 105/140 GHz/ * MW/ 300 sec W7-X 10 1MW/140GHz/ 1800 sec JET just discussions since 2000 Future installations: . ITER 24 1MW/170GHz/3600 sec 2025 . JT-60SA 7 110/138 GHz/100 sec 2019 . DEMO 50 MW/ 230 GHz/ CW • First steps and main events • List of running and near future EC systems • EC systems: aims and content • ITER EC system • Necessary steps from ITER to DEMO • New developments for future EC systems o Higher gyrotron frequency o Multi-frequency operation o Broad band window o Remote steering launcher 8 How ECH works mm-wave beams launched from either the upper or equatorial ports Beam steering from external system (mirrors in upper port) Power absorbed locally, where B satisfies: Microwaves give energy to electrons when electron cyclotron resonance occurs 9 Heating and Current drive source that is both localized and steerable Barrier(window) is possible ECH is a surgical tool that can “pen point” a spot in the plasma cross section to heat plasma and/or drive current Localized: 4cm to 20cm deposition width Useful for: Current Profile Tailoring MHD Control deposit ˜0.8MA from center to mid radius deposit ˜0.2MA inside rotating 4cm island EL center edge UL 10 EC system includes Main components • Gyrotrons (many) • Transmission lines (many) HE11 waveguide or mirrors • Barrier windows (many) Aix components • Launchers (several) • HV and LV power supplies • Control system • Cooling system • Safety EC is used through out the Plasma Discharge Start-up “Provides “spark” to initiate plasma Plasma Current Ramp-up Good absorption when plasma is not “hot” Helps to build up temperature and current Tailors current profile for stabilising plasma Helps to achieve High confinement mode Burn Startup Ramp Burn Ramp Tailors Current profile up down Controls sawtooth and NTMs maintains “hot” plasma Ramp-down Helps to ramp-down plasma softly Tailors current profile to avoid instabilities EC Power 12 ITER EC Targeted Physics Functions EC “App” Matrix Based on existing practices (AUG, DIII-D, JT-60U, TCV, etc) TID: Targeted and Impacts Design // TND Targeted and Not impacting Design 13 • First steps and main events • EC systems: aims and content • List of running and near future EC systems • ITER EC system • Necessary steps from ITER to DEMO • New developments for future EC systems o Higher gyrotron frequency o Multi-frequency operation o Broad band window o Remote steering launcher 14 ITER Electron Cyclotron System 5 Launchers (20MW) 24 Transmission lines 24 sources (24MW) Power Supplies (50MW) Method Advantage Disadvantage Extremely localized heating and current deposition - Indirect heating of ions EC Couples high power Uses external actuators to - Limited long pulse high microwaves to e change deposition location power experience Effectively 100% coupling 15 NTM control Upper Launcher is like a ‘predator drone’: it watches plasma from above and hits each island as they rotate in sight Upper Launcher optics designed for: Deposition 4 to 8cm Power can modulate up to 5kHz 24 beams overlap in plasma (very narrow profiles) Last mirror steers deposition over 50% of plasma 16 Equatorial Launcher Primary Role Note that beams now steer in poloidal direction 17 EC Functional Requirements EC HCD Applications (Baseline and Power Upgrades) First Plasma Operations (inject 6.7MW) Second Plasma Operations (inject 20MW) Upgrade Operations (inject additional ≤20MW) Safety Nuclear Occupational Compliance with Load Specifications Nuclear Vacuum Environmental Seismic Over pressure events Fire Plasma Seismic Combined loads Integration RAMI (reliability, availability, maintainability, inspectability) 18 DAs have chosen the EC System Procurements Divisions 5 Parties provide in-kind procurement of the 4 EC subsystems EU IN JA RF US PS 8 sets 4 main 8 APS/BPS RF Source 6MW 2MW 8MW 8MW TL 24 Launchers 4 (UL) 1 (EL) 19 Plug to Plasma Efficiency Electrical Efficient from Grid to Plasma Requirement: >39% Achieving: between 39 and 44% (does not include services) 20 Actuators: Launchers Upper launcher 4 ports, 8 entries each Control of MHD activity (NTMs) 20MW Switch (≤3 sec) Equatorial launcher: 1 Port, 24 entries Central heating and current drive 21 EC Transmission Line Transmission Line Overview: Length ˜160m Tokamak Power Handling 1.4MW Pulse length 3’600s (25% duty cycle) Power Transmission Efficiency ≥90% Mode conversion efficiency ≥95% Transmission Line Path Microwave Sources 22 Actuators: Transmission Line Universal Polarizer (>99% O or X mode coupling) Polarization change ≤2 sec 24 switches directing power to either EL or UL 8 switches directing power to UL “upper” or “lower” Steering mirrors Switching speed ≤3 sec 23 Safety EC system has to comply with Tritium Confinement Diamond window All-metal valve Shutter Valve 24 RF Sources (Gyrotrons) 170GHz Gyrotrons are rated for: pulse length of 3’600sec 1MW at window with ≥95% TEM00 mode purity LHe free cryomagnets >50% efficiency (Pout/PCollectorin) (ground) JA RF EU IN Challenges: electron beam Mass production High Reliability Higher Power (≥1.0MW) TBD RF power Long life (≥5 years)(~ 1MW) mode convertorHigh mode purity (≥98%) mm-wavesPartial Power modulation Resonator5kHz SC magnet 0.1mT < |Br| < 0.25mT (or Body (~+30kV)less) 1MW 1MW 0.8MW Cathode (~-60kV) 1000s 1000s 100s @~1’000 C 50-55% 53% 25 HVPS: Main and Body for EU and RF gyrotrons Main High Voltage Power Supply Body Power Supply (PSM based) (PSM based) Parameter Value Parameter Value Voltage ∼55kV Voltage ∼35kV Current ∼110A Current <100mA Pulse Length 3’600 sec Pulse Length 3’600 sec Duty cycle 25% Duty cycle 25% Current increased for 1.2 to 1.4 MW Gyrotrons EU contract signed with Ampegon 26 Schedule: Objective at System Level General ITER EC Planning 2025: first plasma (1 UL, 8MW EC for plasma initiation and maybe EL) 2028: second plasma and full 24MW EC system <2035: D-T phase EC manufacturing, assembly and Operation Schedule 2018: Access to RF Building 2018-9: Start installation of PS, Gyrotrons, TL 2023-24: 1 UL plug and 8MW ready for operation 2024: All ex-vessel installed, ≥1 year commissioning for First Plasma 2027: All launchers installed 2028: Full system operating 2031: (Full NB and IC operating) 27 Current activities. Russian team. IAP/GYCOM Gyrotrons/TL components for plasma fusion (2015-2016) • ITER activity • EAST (first ECW experiment) +1 • KSTAR (first delivery in 2015, acceptance test completed) +1 • Asdex Upgrade • TCV • EU DA…. • New developments 28 ITER RF Source prototype False floor removed Gun Coil Power Supply Collector DC coil Power Supply Temperature Monitor X and Y Correction coils Power Supplies Super Conductive Magnet Power CathodeSupply Filament Power Supply Collector Sweep coil Power Supply Ion Pump Power Supply PROTOTYPE OF RF-DA RF POWER SOURCE, TEST REPORT May 11 – 15, 2015, Nizhny Novgorod, Russia Gyrotron together with SCM, MOU and relief load in the support structure left picture Waveguide with terminal load and cooling manifolds top right Operator console with control &protection cubicles bottom right Russian ITER RF Source pre-prototype Gyrotron run test (2014) at 1MW output power with pulse duration 500s and 1000s 1100 regular cut-off internal arc 1000 900 Reliability > 95% 800 New tube conditioning 700 600 500s – 160 pulses 500 pulse duration, s duration, pulse 1000s – 55 pulses 400 300 200 100 0 1 51 101 151 201 251 pulse sequencial number PROTOTYPE
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