Overview of Versatile Experiment Spherical Torus (VEST)
Total Page:16
File Type:pdf, Size:1020Kb
Load more
Recommended publications
-
Engineering Design Evolution of the JT-60SA Project
EngineeringEngineering DesignDesign EvolutionEvolution ofof thethe JTJT --60SA60SA ProjectProject P. Barabaschi, Y. Kamada, S. Ishida for the JT-60SA Integrated Project Team EU: F4E-CEA-ENEA-CNR/RFX-KIT-CRPP-CIEMAT-SCKCEN JA: JAEA 1 JTJT --60SA60SA ObjectivesObjectives •A combined project of the ITER Satellite Tokamak Program of JA-EU (Broader Approach) and National Centralized Tokamak Program in Japan. •Contribute to the early realization of fusion energy by its exploitation to support the exploitation of ITER and research towards DEMO. ITER DEMO Complement Support ITER ITER towards DEMO JT-60SA 2 TheThe NewNew LoadLoad AssemblyAssembly • JT60-U: Copper Coils (1600 T), Ip=4MA, Vp=80m 3 • JT60-SA: SC Coils (400 T), Ip=5.5MA, Vp=135m 3 JTJTJT-JT ---60U60U JTJTJT-JT ---60SA60SA JT-60SA(A ≥2.5,Ip=5.5 MA) ITER (A=3.1,15 MA) 3.0m 6.2m ~2.5m ~4m 1.8m KSTAR (A=3.6, 2 MA) 1.7m EAST (A=4.25,1 MA) 1.1m 3 SST-1 (A=5.5, 0.22 MA) 3 HighHigh BetaBeta andand LongLong PulsePulse • JT-60SA is a fully superconducting tokamak capable of confining break- max even equivalent class high-temperature deuterium plasmas ( Ip =5.5 MA ) lasting for a duration ( typically 100s ) longer than the timescales characterizing the key plasma processes, such as current diffusion and particle recycling. • JT-60SA should pursue full non-inductive steady-state operations with high βN (> no-wall ideal MHD stability limits). 4 4 PlasmaPlasma ShapingShaping • JT-60SA will explore the plasma configuration optimization for ITER and DEMO with a wide range of the plasma shape including the shape of ITER , with the capability to produce both single and double null configurations. -
Past, Present and Future of the US-KSTAR Collaboration Hyeon K
Past, Present and Future of the US-KSTAR Collaboration Hyeon K. Park POSTECH at 2009 US-KSTAR Workshop GA.SanDiego, CA On April 15-16, 2009 Past of the international fusion effort • Three large tokamak era: non-steady state device based on Cu coils (pulse length is limited by the cooling system < ~ 20 sec.) – Tokamak Fusion Test Reactor (USA) 1982-1997, Princeton Plasma Physics Laboratory, USA ¾ Fusion power yield: Q ~ 0.3 from D-T experiment – Joint European Tokamak (EU):1983 – present, Culham, Oxfordshore, UK ¾ Fusion power yield: Q ~ 0.7 from D-T experiment – JT-60U (Japan):1985 - present, Japan Atomic Energy Agency (JAEA), Japan ¾ Q~1.25 extrapolated from D-D experiment Internal view of Internal view of TFTR Internal view of JT60-U JET/plasma discharge Future (ITER) • The goal is "to demonstrate the scientific and technological feasibility of fusion power for peaceful purposes". – Demonstration of fusion power yield; Q (output power/input power) ~10 – International consortium (Europe, Japan, USA, Russia, Korea, China, and India) – Total cost ~ $10 B for ~10 years Physics basis is empirical energy confinement scaling KSTAR-US collaboration (past) • US-KSTAR workshop at GA on May 2004 • Areas of interest (first priority of KSTAR)~$1.62M – Steady-state Technology ($14.3M) ($0.37M) – Control, Stability and AT modes($1.48M) ($0.35M) – Conventional Diagnostics ($ 6.5M) ($0.45M) – Advanced Diagnostics ($2.8M) ($0.2M) – Collaboratory ($1.25M)($0.25M) • US-KSTAR workshop 2005 at Daejeon (active work) • US-KSTAR workshop 2006 at Princeton – FY06 International Collaboration to prepare for KSTAR operation (Finals 04/06; $1352K total) – Total allocation for Institution: PPPL (~500k), GA (~400k), ORNL (~200k), LLNL (~20k), MIT(~40k) Columbia (~100k), Escalated KSTAR progress • US-KSTAR workshop (Sept, 2007), Dajeon, Korea – Korean National Assembly passed the Fusion Energy Developm ent Promotion Act on November 30, 2006. -
TH/P8-21 Transport Simulations of KSTAR Advanced Tokamak
1 TH/P8-21 Transport Simulations of KSTAR Advanced Tokamak Scenarios Yong-Su Na 1), 2), C. E. Kessel 3), J. M. Park 4), J. Y. Kim 1) 1) National Fusion Research Institute, Daejeon, Korea 2) Department of Nuclear Engineering, Seoul National University, Seoul, Korea 3) Princeton Plasma Physics Laboratory, Princeton, NJ, USA 4) Oak Ridge National Laboratory, Oak Ridge, TN, USA e-mail contact of main author: [email protected] Abstract. Predictive modeling of KSTAR operation scenarios are performed with the aim of developing high performance steady state operation scenarios. Various transport codes are employed for this study. Firstly, steady state operation capabilities are investigated with time dependent simulations using a free-boundary transport code. Secondly, reproducibility of high performance steady state operation scenario from an existing tokamak to KSTAR is investigated using the experimental data from other tokamak device. Finally, capability of DEMO-relevant advanced tokamak operation is investigated in KSTAR. From those simulations, it is found that KSTAR is able to establish high performance steady state operation scenarios. The selection of the transport model and the current ramp up scenario is also discussed which have strong influence on target profiles. 1. Introduction As the fusion era is rapidly approaching, the necessity of development of steady state operation scenarios becomes more and more important, particularly for fusion reactor models based on the tokamak concept. In addition to the steady state operation, fusion performance of the tokamak needs to be improved compared with conventional H-modes for developing economically viable fusion power plants. In this context, the, so-called, advanced tokamak (AT) scenarios are being developed aiming at satisfying these two reactor requirements simultaneously. -
H-Mode Transition Physics Close to DN on MAST and Its Applications to Other Tokamaks
20th IAEA FUSION ENERGY CONFERENCE 1-6 November 2004 Vilamoura, Portugal Organized by the International Atomic Energy Agency Hosted by the Government of Portugal through: INSTITUTO SUPERIOR TÉCNICO Centro de Fusão Nuclear www.cfn.ist.utl.pt Book of Abstracts IAEA-CN-116 20th IAEA Fusion Energy Conference 2004 Book of Abstracts Contents Overview (OV) 1 OV/1-1 ·Overview of JT-60U Progress towards Steady-state Advanced Tokamak . 2 OV/1-2 ·Overview of JET results . 2 OV/1-3 ·Development of Burning Plasma and Advanced Scenarios in the DIII-D Tokamak 2 OV/1-4 ·Confinement and MHD stability in the Large Helical Device . 2 OV/1-5 ·Overview of ASDEX Upgrade Results . 3 OV/2-1 ·Overview of Zonal Flow Physics . 3 OV/2-2 ·Steady-state operation of Tokamaks: key physics and technology developments on Tore Supra. 3 OV/2-3 ·Progress Towards High Performance Plasmas in the National Spherical Torus Experiment (NSTX) . 4 OV/2-4 ·Overview of MAST results . 4 OV/2-5 ·Overview of Alcator C-Mod Research Program . 5 OV/3-1 ·Recent Advances in Indirect Drive ICF Target Physics . 5 OV/3-2 ·Laser Fusion research with GEKKO XII and PW laser system at Osaka . 5 OV/3-3 ·Direct-Drive Inertial Confinement Fusion Research at the Laboratory for Laser Energetics: Charting the Path to Thermonuclear Ignition . 5 OV/3-4 ·Acceleration Technology and Power Plant Design for Fast Ignition Heavy Ion Inertial Fusion Energy . 6 OV/3-5Ra ·Progress on Z-Pinch Inertial Fusion Energy . 6 OV/3-5Rb ·Wire Array Z pinch precursors, implosions and stagnation . -
Modeling and Control of Plasma Rotation for NSTX Using
PAPER Related content - Central safety factor and N control on Modeling and control of plasma rotation for NSTX NSTX-U via beam power and plasma boundary shape modification, using TRANSP for closed loop simulations using neoclassical toroidal viscosity and neutral M.D. Boyer, R. Andre, D.A. Gates et al. beam injection - Topical Review M S Chu and M Okabayashi To cite this article: I.R. Goumiri et al 2016 Nucl. Fusion 56 036023 - Rotation and momentum transport in tokamaks and helical systems K. Ida and J.E. Rice View the article online for updates and enhancements. Recent citations - Design and simulation of the snowflake divertor control for NSTX–U P J Vail et al - Real-time capable modeling of neutral beam injection on NSTX-U using neural networks M.D. Boyer et al - Resistive wall mode physics and control challenges in JT-60SA high scenarios L. Pigatto et al This content was downloaded from IP address 128.112.165.144 on 09/09/2019 at 19:26 IOP Nuclear Fusion International Atomic Energy Agency Nuclear Fusion Nucl. Fusion Nucl. Fusion 56 (2016) 036023 (14pp) doi:10.1088/0029-5515/56/3/036023 56 Modeling and control of plasma rotation for 2016 NSTX using neoclassical toroidal viscosity © 2016 IAEA, Vienna and neutral beam injection NUFUAU I.R. Goumiri1, C.W. Rowley1, S.A. Sabbagh2, D.A. Gates3, S.P. Gerhardt3, M.D. Boyer3, R. Andre3, E. Kolemen3 and K. Taira4 036023 1 Department of Mechanical and Aerospace Engineering, Princeton University, Princeton, NJ 08544, USA I.R. Goumiri et al 2 Department of Applied Physics and Applied Mathematics, -
Italy . Frascati Tokamak Upgrade . Superconductors
it enea the italian fusion programme is coordinated by EnEa (agenzia nazionale per le nuove tecnologie, l’energia e lo sviluppo economico sostenibile). EnEa works with linked third parties: universities, research institutes, and industries. institutes carrying out fusion research along with EnEa include plasma physics institute (ifp), Consorzio rfX, national research Council of italy (Cnr), national institute for nuclear physics (infn) and university of padova. about 600 professionals work on fusion research in institutions across italy. enea • EnEa centre at frascati houses the frascati tokamak upgrade (ftu) tokamak, a high- magnetic-field, high-plasma-density tokamak; it investigates radio-frequency plasma heating, control techniques and plasma-wall interaction with liquid metal walls • frascati neutron generator, a medium intensity 14-mev neutron generator, is used for experimental validation of fusion nuclear data and codes. • studies and development of superconductor materials are carried out at the EnEa superconductivity laboratory • EnEa’s high heat flux Components laboratory set up and tested the manufacturing process and a dedicated facility for the fabrication of full scale itEr divertor target prototypes • Design and experimental validation of liquid metal technology for breeding blankets can be done at EnEa centre at Brasimone. ConsoRZio RFX • Consorzio rfX staff are involved in the scientific exploitation and upgrade of the rfX-mod experiment, a flexible device which can be operated both as a high current reversed field pinch -
Introduction to Nuclear Fusion
Introduction to Nuclear Fusion Prof. Dr. Yong-Su Na To build a sun on earth - Open magnetic confinement - Closed magnetic confinement 2 What is closed magnetic confinement? 3 Open Magnetic System B sin 2 min Bmax v|| loss cone loss cone - Suffering from end losses J.P. Freidberg, “Ideal Magneto-Hydro-Dynamics”, lecture note A. A. Harms et al, “Principles of Fusion Energy”, World Scientific (2000) 4 Open Magnetic System Magnetic field Is this motion realistic? ion Dunkin donuts (2010) 5 Closed Magnetic System Magnetic field Donut-shaped vacuum vessel ion 6 Closed Magnetic System 7 Closed Magnetic System Magnetic field R 0 a Plasma needs to be confined ion R0 = 1.8 m, a = 0.5 m in KSTAR 8 Closed Magnetic System Magnetic field R 0 a Plasma needs to be confined ion R0 = 6.2 m, a = 2.0 m in ITER 9 Closed Magnetic System Toroidal Field (TF) coil Magnetic field Toroidal direction Applying toroidal magnetic field ion 3.5 T in KSTAR, 5.3 T in ITER 10 Closed Magnetic System Toroidal Field (TF) coil Toroidal direction Applying toroidal magnetic field 3.5 T in KSTAR, 5.3 T in ITER 11 Closed Magnetic System Toroidal Field (TF) coil Magnetic field Toroidal direction Magnetic field of earth? 0.5 Gauss = 0.00005 T ion 12 http://www.crystalinks.com/earthsmagneticfield.html Closed Magnetic System Magnetic field Magnetic field of earth? 0.5 Gauss = 0.00005 T ion http://www.transformacionconciencia.com/archives/2384 13 Closed Magnetic System Magnetic field ion 14 Lesch, Astrophysics, IPP Summer School (2008) Closed Magnetic System Magnetic field ion electron -
Nuclear Fusion Research Activities at KAERI
Transactions of the Korean Nuclear Society Spring Meeting Jeju, Korea, May 12-13, 2016 Nuclear Fusion Research Activities at KAERI Dong Won Leea, Sun Ho Kima, Seong Ho Jeonga, Byung Hoon Oha aKorea Atomic Energy Research Institute, Republic of Korea *Corresponding author: [email protected] 1. Introduction Large aspect ratio (5.6) High bootstrap current (≥50%) Nuclear fusion is considered to be a next generation Intensive RF heating and current drive (5 clean and sustainable energy due to its inherent safety MW) and abundant fuel resource. In this context, ITER has been built to resolve the scientific and technological issues remained for the ignition at Cadarache in France 3. Research & Development on KSTAR heating since 2006 [1, 2]. Korea has joined the ITER project system and contributed to ITER construction and understanding of plasma physics through KSTAR We have participated in KSTAR construction and (Korea Super Conducting Tokamak Advanced operation using the lessons from the former tokamaks Research) [3]. [4-6] with focus on tokamak heating and current drive KAERI has much experience on fusion plasmas devices such as ICRF and NB since 1996. It provided through KT-1 development and KT-2 planning since KSTAR heating power up to 6MW at present time. 1983. After that we have participated the KSTAR and Especially, NB contributed to achievement of long- ITER projects in various fields. In the present paper, pulse stable H-mode during 40 sec at KSTAR [7]. It these activities at KAERI, especially for Fusion Nuclear will enable KSTAR to achieve high beta long pulse Engineering Development Division were introduced. -
The Advanced Tokamak: Goals, Prospects and Research Opportunities Amanda Hubbard MIT Plasma Science and Fusion Center with Thanks to Many Contributors, Including A
The Advanced Tokamak: Goals, prospects and research opportunities Amanda Hubbard MIT Plasma Science and Fusion Center with thanks to many contributors, including A. Garafolo, C. Greenfield, C. Kessel, D. Meade, M. Murakami, F. Najmabadi, T. Taylor Opinions are my own… GCEP Fusion Energy Workshop on Opportunities for Fundamental Research and Breakthrough in Nuclear Fusion Princeton, NJ May 1-2 2006 The Advanced Tokamak • Introduction: What is an ‘advanced tokamak’? • The AT vision for fusion energy – Drawing heavily on ARIES studies. • Current results and near-term prospects – Focusing here on US program. • AT on ITER: What we will (and won’t) learn. • Research Opportunities: ideas to advance and accelerate fusion energy prospects. To start the discussion…. An “advanced tokamak” device is, in terms of magnetic configuration, simply a TOKAMAK Pure toroidal field does not confine charged particles Tokamak needs a toroidal current for stability. Adding poloidal field does Current conventionally driven by tranformer; confine charged particles. - Current is driven around central solenoid. Produced by toroidal current. Inherently NOT steady-state. Tokamaks lead other configurations in fusion performance, are approaching ‘breakeven’ ITER D. Meade, ARIES workshop 4/24/05 “Conventional” tokamak operation will be primary mode of operation on ITER • Heating applied mainly on-axis, inductive current drive, profiles relax to ‘natural’ state. • Much experience worldwide, good confidence in extrapolation to burning plasma conditions. – This will allow -
Poster Session 1 Author Title Session Nr
Poster Session 1 Author Title Session Nr. Chen, Y. Design of Real-time Data Acquisition System for POlarimeter- 1,3 INTerferometer diagnostic Fuchs, J.C. CLISTE equilibrium reconstruction in ASDEX Upgrade using 1 toroidally distributed magnetic measurements and possible implications on the plasma position control Gerkšič, S. SVD-based fast online MPC for ITER plasma current and shape 1 control Guo, Y. Preliminary results of a new MIMO plasma shape controller for 1 EAST Huang, Y. Improvement of GPU parallel real-time equilibrium reconstruction 1 for plasma control Li, C.C. Preliminary Implementation of the Real-time Data Sharing System 1,7 Based on RFM for EAST Manduchi, G. A Portable Control And Data Acquisition Solution 1 Shah, M. FPGA based Trigger and Timing System for Aditya-U Tokamak 1 Operation and Control Shin, G.W. Automatic Detection of L-H Transition in KSTAR by Support Vector 1 Machine Signoret, J. Coupling Plasma Control System and Pulse Schedule Editor for 1 WEST Operation StStepanov, DD. ITER CODAC OOperation ti RRequest t Gatekeeper: G t k First Fi t 1 Implementation Varshney, S. Design maturity of Plant Instrumentation and Control for ITER 1 XRCS-Survey Vega, J. Real-time implementation with FPGA-based DAQ system of a 1 probabilistic disruption predictor from scratch Wang, Y. Closed-loop control-oriented system identification for EAST 1 plasma shape response model Wu, K. Radiative Feedback for Divertor Heat Spread on EAST 1 Xiao, B.J. Model-based plasma vertical stabilization and position control at 1 EAST Yeole, Y.G. An Automation of Vacuum System for SMARTEX-C Yuan, Q.P. -
Nuclear Fusion Power – an Overview of History, Present and Future
International Journal of Advanced Network, Monitoring and Controls Volume 04, No.04, 2019 Nuclear Fusion Power – An Overview of History, Present and Future Stewart C. Prager Department of Physics University of Wisconsin – Madison Madison, WI 53706, USA E-mail: [email protected] Summary—Fusion power offers the prospect of an allowing the nuclei to fuse together. Such conditions almost inexhaustible source of energy for future can occur when the temperature increases, causing the generations, but it also presents so far insurmountable ions to move faster and eventually reach speeds high engineering challenges. The fundamental challenge is to enough to bring the ions close enough together. The achieve a rate of heat emitted by a fusion plasma that nuclei can then fuse, causing a release of energy. exceeds the rate of energy injected into the plasma. The main hope is centered on tokamak reactors and II. FUSION TECHNOLOGY stellarators which confine deuterium-tritium plasma In the Sun, massive gravitational forces create the magnetically. right conditions for fusion, but on Earth they are much Keywords-Fusion Energy; Hydrogen Power; Nuclear Fusion harder to achieve. Fusion fuel – different isotopes of hydrogen – must be heated to extreme temperatures of I. INTRODUCTION the order of 50 million degrees Celsius, and must be Today, many countries take part in fusion research kept stable under intense pressure, hence dense enough to some extent, led by the European Union, the USA, and confined for long enough to allow the nuclei to Russia and Japan, with vigorous programs also fuse. The aim of the controlled fusion research underway in China, Brazil, Canada, and Korea. -
European Consortium for the Development of Fusion Energy European Consortium for the Development of Fusion Energy CONTENTS CONTENTS
EuropEan Consortium for thE DEvElopmEnt of fusion EnErgy EuropEan Consortium for thE DEvElopmEnt of fusion EnErgy Contents Contents introDuCtion ReseaRCH units CooRDinating national ReseaRCH FoR euRofusion 16 agenzia nazionale per le nuove tecnologie, l’energia e lo sviluppo economico sostenibile (enea), italy euRofusion: eMboDying tHe sPiRit oF euRoPean CollaboRation 17 FinnFusion, finland 4 the essence of fusion 18 fusion@Öaw, austria the tantalising challenge of realising fusion power 19 hellenic fusion research unit (Hellenic Ru), greece the history of European fusion collaboration 20 institute for plasmas and nuclear fusion (iPFn), portugal 5 Eurofusion is born 21 institute of solid state physics (issP), latvia the road from itEr to DEmo 22 Karlsruhe institute of technology (Kit), germany 6 Eurofusion facts at a glance 23 lithuanian Energy institute (lei), lithuania 7 itEr facts at a glance 24 plasma physics and fusion Energy, Department of physics, technical university of Denmark (Dtu), Denmark JEt facts at a glance 25 plasma physics Department, wigner Fusion, hungary 8 infographic: Eurofusion devices and research units 26 plasma physics laboratory, Ecole royale militaire (lPP-eRM/KMs), Belgium 27 ruder Boškovi´c institute, Croatian fusion research unit (CRu), Croatia 28 slovenian fusion association (sFa), slovenia 29 spanish national fusion laboratory (lnF), CiEmat, spain 30 swedish research Council (vR), sweden rEsEarCh unit profilEs 31 sylwester Kaliski institute of plasma physics and laser microfusion (iPPlM), poland 32 the institute