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Fusion Research in Iran FUSION RESEARCH IN IRAN CHILE-SANTIAGO– MARCH 2017 – S. MESHKANI Due to an increase in world population and more energy consumption, it will be difficult to rely on the fossil fuel as energy source. Without improvements in efficiency we will need 80% more energy by 2020 Even with efficiency improvements at the limit of technology we would still need 40% more energy. Growth in population and energy demand (1987-2020) 2 Fuel needed for one year of power plant operations (1000MW) 3 4 Escalation of investment magnetic fusion science by using “superconductor” technology to produce the magnetic bottle 5 ITER Parameters Major radius 6.2 m Minor radius 2 m Volume 830 m3 Plasma current 15 MA Toroidal field 5.3 T Density 1020 m-3 Peak Temperature 2108 K Fusion Power 500 MW Plasma Burn 300-500 s 6 Different parts of ITER which designed and constructed by 9 members CENTRAL TOROIDAL FIELD SOLENOID MODEL COIL MODEL COIL Height 4 m Radius 3.5 m Width 3 m Height 2.8m Bmax=7.8 T Bmax=13 T 0.6 T/sec BLANKET MODULE HIP Joining Tech VACUUM VESSEL SECTOR Double-Wall, ± 5 mm REMOTE MAINTENANCE OF REMOTE MAINTENANCE OF BLANKET DIVERTOR CASSETTE DIVERTOR CASSETTE AND PFCs 20 MW/m2 Attachment Tolerance ± 2 mm 4 t blanket sector ±0.25 mm 7 Fusion and plasma education in Iran • Scientific Member Boards related to fusion energy: 37 • MSc students graduated in plasma and fusion engineering: 285 • PhD student graduated in fusion engineering and fusion plasma: 22 Tabriz University I. A. University Mashhad Branch Tehran I. A. University Atomic Energy Org. of Iran Isfahan Amir Kabir University University Shiraz University A network of fusion engineering scientists and researchers in Iran has been developed to promote the fusion program among all active organizations and universities in Iran. 8 Fusion and plasma education in Iran Because of young population in Iran, there are many applicant for Master and PhD position as well as fusion engineering and fusion plasma. Three Institutions are almost leaders for fusion program in Iran which are geographically in Tehran and they have small tokamaks in medium field and ohmically heating systems: • I. A. University • IR-T1 Tokamak (1994) • Atomic Energy Organization of Iran • Alvand Tokamak (1973, Italy-Iran) • Damavand Tokamak (1995, TVD, Russia) • Amir Kabir University • Alborz Tokamak (Under construction -2017, Iran) 9 10 IR-T1 Tokamak Parameter Value Major Radius 45 cm Minor Radius 12.5 cm Toroidal Field 0.8 T Plasma Current < 40 kA 19 -3 Plasma Density 1.5 × 10 m Electron Temperature ~180 eV Discharge Duration 30-35 ms Vacuum Vessel Type Stainless Steel 316L Major Heating System Ohmic Heating Pre-ionization RF Electric Field (8 MHz) & Thermoelectric (Filament) Limiter Type and Ring Limiter (Tungsten) & Diameter 23.00 cm Plasma Type Hydrogen Zeff 1.5 11 IR-T1 Diagnostics Diagnostic Number Soft X-Ray Analyzer Visible 23 Horizontal & Spectrometer 10 Vertical Channels Electro Magnetic winding (Mirnov 32 Coils) Rogowski Coils 5 16 Channels Rack Probe (Vertical) 1 Movable Langmuir Probe 1 (Horizontal) Hard X-Ray Detectors (Scintillator) 3 RGA (Residual Gas Analyzer) 1 Limiter biasing system (± 400 volt) 1 Dual channel spectrometer (Ava space uls 3648) 400-550 nm High 1 resolution RHF (resonant helical magnetic field 1 Langmuir Ball-pen probe 1 Capacitive probe 1 Mach probe 1 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 Study of Particle Transport in Plasma Poloidal array of Langmuir probes in IR-T1 Tokamak Radial array of Langmuir probes (Rake probe) in IR-T1 Tokamak 27 Direct measurement of Plasma Potential and Electron Temperature Langmuir Ball-Pen Probe 28 Study of Electric Fluctuations Capacitive Probe 29 Limiter Biasing System The power supply is a high voltage and high current. Capacitor bank charged by AC power. Bias voltage is applied in the range of -380 V< V< +380 V. Bias current is in the range of -40A< I < +40A. To change the polarity of the electric field, there is a 2-mode switch between limiter and bias system. Biased Limiter can move maximum of 1.25 cm inside the plasma. 30 RHF in IR-T1 The RHF in IR-T1 is created by two sets of local helical fields that are installed outside the vacuum vessel. I=70-100A B≅ ퟐ. ퟑ × ퟏퟎ −ퟒ T The minor radii of these helical windings are 22cm (L = 2;m = 2, n = 1) and 23cm (L = 3;m = 3, n = 1). 31 Main Hard X-ray Spectroscopy in MCA Amplifier IR-T1 Tokamak Pre- Amplifier Scintillator Detector Detector Position HV A very sensitive detector, 3 inches The detector was placed at almost 40 Supply NaI(Tl) crystal was utilized to detect the degrees with respect to the central hard X-ray spectra from IR-T1 axis of the chamber to detect the most VD TOKAMAK. P/V ratio of NaI(Tl) crystal spectra. is 10 : 1. This is equivalent to an energy resolution of 7.0% at 662 keV. Scintillation Detector Tokamak 32 Measurement of Electron Temperature by LBP Probe c e a b d f Increase of electron temperature after Increase of plasma current after Increase of plasma potential after applying positive biased voltage applying positive biased voltage applying positive biased voltage Decrease of diffusion coefficient after applying positive biased voltage 33 Study of Particle Transport by Langmuir Probe a Decrease of radial particle flux after applying positive biased voltage Decrease of diffusion coefficient b after applying positive biased voltage 34 Study of Hard X-Ray emitted by IR-T1 Tokamak Figures show 10 time intervals of 5 ms for the number of hard x-ray photon counts emitted by IR-T1 TOKAMAK. It can be seen that the most number of counts are in the range of 100-200 keV. And they mostly appeared after 15ms. 35 Improving plasma confinement by applying biased voltage a f d b g e c h Reducing the number of X-ray photons in the ranges of 100-200 Increase of plasma confinement time and keV after applying biased voltage Decrease of Energy loss in IR-T1 plasma current after applying biased plasma after applying biased voltage voltage 36 Decrease of Energy Loss in IR-T1 Tokamak by Applying RHF a c e b d f Increase of plasma confinement time Decrease of diffusion coefficient Decrease of Hard X-ray Energy after and plasma current after applying after applying RHF applying RHF RHF 37 Decrease of Energy Loss with Changing Main Magnetic Fields Change in Toroidal Field Change in Vertical Field a c Increasing Toroidal and Vertical magnetic field resulted in plasma improvement both in current and confinement. Less Hard X-ray spectra was emitted due to the rise of Toroidal d and Vertical magnetic field. b 38 Damavand Tokamak (Atomic Energy Organization of Iran) Elongated Cross Section R = 36cm,a=10cm,b=7cm BMAX = 1.2T Plasma Current = 30-35kA Plasma Duration= 20-22ms Te: 250-300 eV Ti : 100-150 eV Pre Ionization : Magnetron 39 R&Z Feedback control 39 T9 Tokamak 1973-76 T12 Tokamak 1976-83 TVD Tokamak 1988-92 Damavand 1994-Now 40 Typical Shot in Damavand Tokamak a) Plasma current, b) loop voltage, c) Hard x-ray and d) Hβ 4860 Å 41 (a):Plasma Current, (b):loop Voltage, (c):HX-Ray, (d):Hβ 4860Å Emission Main research branches in Damavand Tokamak • Plasma Control Algorithms • Diagnostic systems • Theory research 42 Alvand Tokamak (Atomic Energy Organization of Iran) Alvand Parameters Parameters Value Major radius(R) 0.456 m Minor radius 0.126 m Plasma Current 35 kA Toroidal magnetic field 0.8 Tesla Plasma Current 30 kA Heating System Ohmic 43 Alborz Tokamak (Amir Kabir University) Under construction -2017 Alborz Parameters Parameters Value Major radius(R) 0.45 m Minor radius 0.15 m Plasma Current 35 kA Toroidal magnetic 0.85 Tesla field Plasma Current 30 kA Heating System Ohmic 44 Comprehensive plan of action and implementation phases of the road map of IR Iran comprehensive program based on the motives and goals: 1. The team qualified for the preparation of the road map. 2. Identification of potentials in the country related to Fusion. 3. The collection offers an effective part of the National Project Fusion Country o Categorizing the common and independent issues, and the internal memorandum in charge of the assigned missions. 4. Create an organizational structure with a national approach. 45 Conceptual Design for Iran National Reactor 1. Establishing the national project organization Support staff, 2. Forecast a R & D research center in order to support the needs of the project. technical and 3. Feasibility domestic and international cooperation professional 4. Establishment of vocational training centers and higher education needed on-site 5. Planning how to begin operating reactor construction 1. Calculate the required land for the reactor site and geotechnical studies. 2. Security analysis Site Location 3. Environmental Studies and Health and residual waste. 4. Water utilities and energy supply studies 5. Economic analysis of the region in terms of transport and industrial facilities 46 Conceptual Design for Iran National Reactor 1. Preparation for the project included the need for the project 2. Full descriptions of devices and systems Define the 3. Describe the technical, operational and mission tokamak reactor 4. Obtaining the priority list and classify them based on the specifications of the system Problem 5. The field research (collecting information, resources and records 6. Identify research centers elsewhere in this issue, the classification results of their research is the possibility to communicate via two-way communication 1. Basic definitions, the introduction of mathematical equations governed by physical parameters and reactor physics Definition 2.
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