Nuclear Fusion Power – an Overview of History, Present and Future

Total Page:16

File Type:pdf, Size:1020Kb

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. program is to achieve 'ignition', which occurs when Initially, fusion research in the USA and USSR was enough fusion reactions take place for the process to linked to atomic weapons development, and it become self-sustaining, with fresh fuel then being remained classified until the 1958 Atoms for Peace added to continue it. Once ignition is achieved, there is conference in Geneva. Following a breakthrough at the net energy yield – about four times as much as with Soviet tokamak, fusion research became 'big science' in nuclear fission. According to the Massachusetts the 1970s. But the cost and complexity of the devices Institute of Technology (MIT), the amount of power involved increased to the point where international co- produced increases with the square of the pressure, so operation was the only way forward. doubling the pressure leads to a fourfold increase in energy production. Fusion powers the Sun and stars as hydrogen atoms fuse together to form helium, and matter is converted With current technology, the reaction most readily into energy. Hydrogen, heated to very high feasible is between the nuclei of the two heavy forms temperatures changes from a gas to plasma in which (isotopes) of hydrogen – deuterium (D) and tritium (T). Each D-T fusion event releases 17.6 MeV (2.8 x 10- the negatively-charged electrons are separated from the 12 joule, compared with 200 MeV for a U-235 fission positively-charged atomic nuclei (ions). Normally, a fusion is not possible because the strongly repulsive and 3-4 MeV for D-D fusion). On a mass basis, the D- electrostatic forces between the positively charged T fusion reaction releases over four times as much nuclei prevent them from getting close enough together energy as uranium fission. Deuterium occurs naturally to collide and for fusion to occur. However, if the in seawater (30 grams per cubic metre), which makes it conditions are such that the nuclei can overcome the very abundant relative to other energy resources. electrostatic forces to the extent that they can come Tritium occurs naturally only in trace quantities within a very close range of each other, then the (produced by cosmic rays) and is radioactive, with a attractive nuclear force (which binds protons and half-life of around 12 years. Usable quantities can be neutrons together in atomic nuclei) between the nuclei made in a conventional nuclear reactor, or in the will outweigh the repulsive (electrostatic) force, present context, bred in a fusion system from lithium. DOI: 10.21307/ijanmc-2019-064 1 International Journal of Advanced Network, Monitoring and Controls Volume 04, No.04, 2019 b Lithium is found in large quantities (30 parts per III. MAGNETIC CONFINEMENT million) in the Earth's crust and in weaker In magnetic confinement fusion (MCF), hundreds concentrations in the sea. of cubic metres of D-T plasma at a density of less than In a fusion reactor, the concept is that neutrons a milligram per cubic metre are confined by a magnetic generated from the D-T fusion reaction will be field at a few atmospheres pressure and heated to absorbed in a blanket containing lithium which fusion temperature. surrounds the core. The lithium is then transformed Magnetic fields are ideal for confining a plasma into tritium (which is used to fuel the reactor) and because the electrical charges on the separated ions and helium. The blanket must be thick enough (about 1 electrons mean that they follow the magnetic field lines. metre) to slow down the high-energy (14 MeV) The aim is to prevent the particles from coming into neutrons. The kinetic energy of the neutrons is contact with the reactor walls as this will dissipate their absorbed by the blanket, causing it to heat up. The heat heat and slow them down. The most effective magnetic energy is collected by the coolant (water, helium or Li- configuration is toroidal, shaped like a doughnut, in Pb eutectic) flowing through the blanket and, in a which the magnetic field is curved around to form a fusion power plant, this energy will be used to generate closed loop. For proper confinement, this toroidal field electricity by conventional methods. If insufficient must have superimposed upon it a perpendicular field tritium is produced, some supplementary source must component (a poloidal field). The result is a magnetic be employed such as using a fission reactor to irradiate field with force lines following spiral (helical) paths heavy water or lithium with neutrons, and extraneous that confine and control the plasma. tritium creates difficulties with handling, storage and transport. There are several types of toroidal confinement system, the most important being tokamaks, The difficulty has been to develop a device that can stellarators and reversed field pinch (RFP) devices. heat the D-T fuel to a high enough temperature and confine it long enough so that more energy is released In a tokamak, the toroidal field is created by a series through fusion reactions than is used to get the reaction of coils evenly spaced around the torus-shaped reactor, going. While the D-T reaction is the main focus of and the poloidal field is created by a system of attention, long-term hopes are for a D-D reaction, but horizontal coils outside the toroidal magnet structure. this requires much higher temperatures. A strong electric current is induced in the plasma using a central solenoid, and this induced current also In any case, the challenge is to apply the heat to contributes to the poloidal field. In a stellarator, the human needs, primarily generating electricity. The helical lines of force are produced by a series of coils energy density of fusion reactions in gas is very much which may themselves be helical in shape. Unlike less than for fission reactions in solid fuel, and as noted tokamaks, stellarators do not require a toroidal current the heat yield per reaction is 70 times less. Hence to be induced in the plasma. RFP devices have the thermonuclear fusion will always have a much lower same toroidal and poloidal components as a tokamak, power density than nuclear fission, which means that but the current flowing through the plasma is much any fusion reactor needs to be larger and therefore stronger and the direction of the toroidal field within more costly, than a fission reactor of the same power the plasma is reversed. output. In addition, nuclear fission reactors use solid fuel which is denser than thermonuclear plasma, so the In tokamaks and RFP devices, the current flowing energy released is more concentrated. Also the neutron through the plasma also serves to heat it to a energy from fusion is higher than from fission – 14.1 temperature of about 10 million degrees Celsius. MeV instead of about 2 MeV, which presents Beyond that, additional heating systems are needed to significant challenges regarding structural materials. achieve the temperatures necessary for fusion. In stellarators, these heating systems have to supply all At present, two main experimental approaches are the energy needed. being studied: magnetic confinement and inertial confinement. The first method uses strong magnetic The tokamak (toroidalnya kamera ee magnetnaya fields to contain the hot plasma. The second involves katushka–torus-shaped magnetic chamber) was compressing a small pellet containing fusion fuel to designed in 1951 by Soviet physicists Andrei Sakharov extremely high densities using strong lasers or particle and Igor Tamm. Tokamaks operate within limited beams. parameters outside which sudden losses of energy confinement (disruptions) can occur, causing major thermal and mechanical stresses to the structure and 2 International Journal of Advanced Network, Monitoring and Controls Volume 04, No.04, 2019 walls. Nevertheless, it is considered the most A completely different concept, the 'Z-pinch' (or promising design, and research is continuing on 'zeta pinch'), uses a strong electrical current in a plasma various tokamaks around the world. to generate X-rays, which compress a tiny D-T fuel cylinder. Research is also being carried out on several types of stellarator. Lyman Spitzer devised and began work V.
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.
    [Show full text]
  • STATUS of FUSION ENERGY Impact & Opportunity for Alberta Volume II
    STATUS OF FUSION ENERGY Impact & Opportunity for Alberta Volume II Appendices Prepared by Alberta/Canada Fusion Energy Program March 2014 ALBERTA COUNCIL OF TECHNOLOGIES Gratefully acknowledges the support of: Alberta Energy Stantec Corporation University of Alberta Alberta/Canada Fusion Energy Advisory Committee Gary Albach Nathan Armstrong Brian Baudais Will Bridge Robert Fedosejevs Peter Hackett Chris Holly Jerry Keller Brian Kryska Axel Meisen Rob Pitcairn Klaas Rodenburg John Rose Glenn Stowkowy Martin Truksa Gary Woloshyniuk Perry Kinkaide Allan Offenberger A special thank you is extended to the institutions (identified in this report) that were visited and to the many persons who so graciously hosted our site visits, provided the briefing material presented in this status report and thereby assisted our fusion assessment. Report Authors Allan Offenberger Robert Fedosejevs Klaas Rodenburg Perry Kinkaide Contact: Dr. Perry Kinkaide [email protected] 780-990-5874 Dr. Allan Offenberger [email protected] 780-483-1740 i TABLE OF CONTENTS Page List of Acronyms ………………………………………………………………………….. iii List of Figures……………………………………………………………………………… iv Appendix A: Assessment of Major Global Fusion Technologies 1.0 Context - Global Energy Demand……………………………………………………… 1 1.0.1 Foreward ……………………………………………………………………… 1 1.0.2 Energy Trends………………………………………………………………… 2 1.0.3 Energy From Fusion Reactions……………………………………………… 4 1.1 Major Approaches to Fusion Energy………………………………………………….. 7 1.1.1 Introduction……………………………………………………………………. 7 1.1.2 Fusion Reactions & the Fuel Cycle………………………………………….. 8 1.1.3 IFE Approaches to Fusion…………………………………………………… 11 1.1.3.1 Introduction………………………………………………………….. 11 1.1.3.2 Indirect Drive…………………………………………………………14 1.1.3.3 Direct Drive…………………………………………………………. 16 1.1.3.4 Fast Ignition………………………………………………………… 17 1.1.3.5 Shock Ignition………………………………………………………..19 1.1.3.6 IFE Power Reactor Systems……………………………………….20 1.1.3.7 Modeling Codes…………………………………………………….
    [Show full text]
  • Controlled Nuclear Fusion
    Controlled Nuclear Fusion HANNAH SILVER, SPENCER LUKE, PETER TING, ADAM BARRETT, TORY TILTON, GABE KARP, TIMOTHY BERWIND Nuclear Fusion Thermonuclear fusion is the process by which nuclei of low atomic weight such as hydrogen combine to form nuclei of higher atomic weight such as helium. two isotopes of hydrogen, deuterium (composed of a hydrogen nucleus containing one neutrons and one proton) and tritium (a hydrogen nucleus containing two neutrons and one proton), provide the most energetically favorable fusion reactants. in the fusion process, some of the mass of the original nuclei is lost and transformed to energy in the form of high-energy particles. energy from fusion reactions is the most basic form of energy in the universe; our sun and all other stars produce energy through thermonuclear fusion reactions. Nuclear Fusion Overview Two nuclei fuse together to form one larger nucleus Fusion occurs in the sun, supernovae explosion, and right after the big bang Occurs in the stars Initially, research failed Nuclear weapon research renewed interest The Science of Nuclear Fusion Fusion in stars is mostly of hydrogen (H1 & H2) Electrically charged hydrogen atoms repel each other. The heat from stars speeds up hydrogen atoms Nuclei move so fast, they push through the repulsive electric force Reaction creates radiant & thermal energy Controlled Fusion uses two main elements Deuterium is found in sea water and can be extracted using sea water Tritium can be made from lithium When the thermal energy output exceeds input, the equation is self-sustaining and called a thermonuclear reaction 1929 1939 1954 1976 1988 1993 2003 Prediction Quantitativ ZETA JET Project Japanese Princeton ITER using e=mc2, e theory Tokomak Generates that energy explaining 10 from fusion is fusion.
    [Show full text]
  • Nuclear Fusion
    Copyright © 2016 by Gerald Black. Published by The Mars Society with permission NUCLEAR FUSION: THE SOLUTION TO THE ENERGY PROBLEM AND TO ADVANCED SPACE PROPULSION Gerald Black Aerospace Engineer (retired, 40+ year career); email: [email protected] Currently Chair of the Ohio Chapter of the Mars Society Presented at Mars Society Annual Convention, Washington DC, September 22, 2016 ABSTRACT Nuclear fusion has long been viewed as a potential solution to the world’s energy needs. However, the government sponsored megaprojects have been floundering. The two multi-billion- dollar flagship programs, the International Tokamak Experimental Reactor (ITER) and the National Ignition Facility (NIF), have both experienced years of delays and a several-fold increase in costs. The ITER tokamak design is so large and complex that, even if this approach succeeds, there is doubt that it would be economical. After years of testing at full power, the NIF facility is still far short of achieving its goal of fusion ignition. But hope is not lost. Several private companies have come up with smaller and simpler approaches that show promise. This talk highlights the progress made by one such private company, namely LPPFusion (formerly called Lawrenceville Plasma Physics). LPPFusion is developing focus fusion technology based on the dense plasma focus device and hydrogen-boron 11 fuel. This approach, if it works, would produce a fusion power generator small enough to fit in a truck. This device would produce no radioactivity, there would be no possibility of a meltdown or other safety issues, and it would be more economical than any other source of electricity.
    [Show full text]
  • NEWSLETTER Issue No. 7 September 2017
    NEWSLETTER September 2017 Issue no. 7 Nuclear Industry Group Newsletter September 2017 Contents Notes from the Chair ................................................................................... 3 IOP Group Officers Forum .......................................................................... 4 NIG Committee Elections ............................................................................ 6 Nuclear Industry Group Career Contribution Prize 2017 .......................... 7 Event – Gen IV Reactors by Richard Stainsby (NNL) ................................ 8 Event – Nuclear Security by Robert Rodger (NNL) and Graham Urwin (RWM) ......................................................................................................... 12 Event – The UK’s Nuclear Future by Dame Sue Ion ................................ 13 Event – Regulatory Challenges for Nuclear New Build by Mike Finnerty. .................................................................................................................... 15 Event – European Nuclear Young Generation Forum ............................. 18 Event – Nuclear Fusion, 60 Years on from ZETA by Chris Warrick (UKAEA), Kate Lancaster (York Plasma Institute), David Kingham (Tokamak Energy) and Ian Chapman (UKAEA) ....................................... 19 IOP Materials and Characterisation Group Meetings .............................. 25 “Brexatom” – the implications of the withdrawal for the UK from the Euratom Treaty. ........................................................................................
    [Show full text]
  • Reactor Potential for Magnetized Target Fusion
    TR.TA-A Report ISSN 1102-2051 VETENSKAP OCH ISRN KTH/ALF/--01/2--SE 1ONST KTH-ALF--01-2 KTH Reactor Potential for Magnetized Target Fusion Jon-Erik Dahlin Research and Training programme on CONTROLLED THERMONUCLEAR FUSION AND PLASMA PHYSICS (Association EURATOM/NFR) FUSION PLASMA PHYSICS ALFV N LABORATORY ROYAL INSTITUTE OF TECHNOLOGY SE-100 44 STOCKHOLM SWEDEN PLEASE BE AWARE THAT ALL OF THE MISSING PAGES IN THIS DOCUMENT WERE ORIGINALLY BLANK TRITA-ALF-2001-02 ISRN KTH/ALF/--01/2--SE Reactor Potential for Magnetized Target Fusion J.-E. Dahlin VETENSKAP OCH KONST Stockholm, June 2001 The Alfven Laboratory Division of Fusion Plasma Physics Royal Institute of Technology SE-100 44 Stockholm, Sweden (Association EURATOM/NFR) Printed by Alfven Laboratory Fusion Plasma Physics Division Royal Institute of Technology SE-100 44 Stockholm Abstract Magnetized Target Fusion (MTF) is a possible pathway to thermonuclear fusion different from both magnetic fusion and inertial confinement fusion. An imploding cylindrical metal liner compresses a preheated and magnetized plasma configuration until thermonuclear conditions are achieved. In this report the Magnetized Target Fusion concept is evaluated and a zero-dimensional computer model of the plasma, liner and circuit as a connected system is designed. The results of running this code are that thermonuclear conditions are achieved indeed, but only during a very short time. At peak compression the pressure from the compressed plasma and mag- netic field is so large reversing the liner implosion into an explosion. The time period of liner motion reversal is termed the dwell time and is crucial to the performance of the fusion system.
    [Show full text]
  • Europe for Inertial Confinement Fusion
    EuropeEurope forfor InertialInertial ConfinementConfinement FusionFusion Technology Watch Workshop on IFE-KIT Madrid March 22, 2010 Jiri Ullschmied Association EURATOM IPP.CR PALS Research Centre, a joint laboratory of the Institute of Physics and Institute of Plasma Physics, Academy of Sciences of the Czech Republic www.pals.cas.cz Paper Layout State of the art - where are we now Lasers on the path to fusion National Ignition Facility Indirect drive / direct drive European lasers, LMJ Coordinated European effort in the laser research Various ignition scenarios - EU KIT contributions SWOT Summary State of the art - where are we now Steadily increasing progress in laser technology since 1960, lasers becoming the most dynamic field of physical research in the last decade. Megajoule and multi-PW lasers have become reality, laser beam focused intensity has been increased up to 1022 W/cm2 (Astra, UK). Last-generation high-power lasers - an unmatched tool for high-energy density physical research and potential fusion drivers. High-energy lasers worldwide Lasers on the path to Fusion Max output energy of single beam systems (Nd-glass, iodine, KrF) in the 1-10 kJ range, while EL > 1 MJ is needed for central ignition => multi-beam laser systems. Various fast ignition schemes are have been proposed, which should decrease the required energy by an order of magnitude. History and future of IFE lasers HiPER Three main tasks demonstrate ignition and burn demonstrate high energy gain develop technology for an IFE power plant Ignition to be demonstrated at NIF (2010?) and LMJ lasers. The natural next step: HiPER. National Ignition Facility NIF is a culmination of long line of US Nd-glass laser systems Nova, OMEGA and NIF shot rates measured in shots/day.
    [Show full text]
  • Digital Physics: Science, Technology and Applications
    Prof. Kim Molvig April 20, 2006: 22.012 Fusion Seminar (MIT) DDD-T--TT FusionFusion D +T → α + n +17.6 MeV 3.5MeV 14.1MeV • What is GOOD about this reaction? – Highest specific energy of ALL nuclear reactions – Lowest temperature for sizeable reaction rate • What is BAD about this reaction? – NEUTRONS => activation of confining vessel and resultant radioactivity – Neutron energy must be thermally converted (inefficiently) to electricity – Deuterium must be separated from seawater – Tritium must be bred April 20, 2006: 22.012 Fusion Seminar (MIT) ConsiderConsider AnotherAnother NuclearNuclear ReactionReaction p+11B → 3α + 8.7 MeV • What is GOOD about this reaction? – Aneutronic (No neutrons => no radioactivity!) – Direct electrical conversion of output energy (reactants all charged particles) – Fuels ubiquitous in nature • What is BAD about this reaction? – High Temperatures required (why?) – Difficulty of confinement (technology immature relative to Tokamaks) April 20, 2006: 22.012 Fusion Seminar (MIT) DTDT FusionFusion –– VisualVisualVisual PicturePicture Figure by MIT OCW. April 20, 2006: 22.012 Fusion Seminar (MIT) EnergeticsEnergetics ofofof FusionFusion e2 V ≅ ≅ 400 KeV Coul R + R V D T QM “tunneling” required . Ekin r Empirical fit to data 2 −VNuc ≅ −50 MeV −2 A1 = 45.95, A2 = 50200, A3 =1.368×10 , A4 =1.076, A5 = 409 Coefficients for DT (E in KeV, σ in barns) April 20, 2006: 22.012 Fusion Seminar (MIT) TunnelingTunneling FusionFusion CrossCross SectionSection andand ReactivityReactivity Gamow factor . Compare to DT . April 20, 2006: 22.012 Fusion Seminar (MIT) ReactivityReactivity forfor DTDT FuelFuel 8 ] 6 c e s / 3 m c 6 1 - 0 4 1 x [ ) ν σ ( 2 0 0 50 100 150 200 T1 (KeV) April 20, 2006: 22.012 Fusion Seminar (MIT) Figure by MIT OCW.
    [Show full text]
  • Inertial Fusion Power Development:Path for Global Warming Suppression
    Inertial Fusion Power Development:Path for Global Warming Suppression EU:France, UK,etc. US: LLNL, SNL, U. Rochester East Asia: Japan, China,etc. Kunioki Mima Institute of Laser Engineering, Osaka University IAEA- FC 2008, 50 years’ Ann. of Fusion Res. , Oct.15, 2008, Geneva, SW Outline • Brief introduction and history of IFE research • Frontier of IFE researches Indirect driven ignition by NIF/LMJ Ignition equivalent experiments for fast ignition • IF reactor concept and road map toward power plant IFE concepts Several concepts have been explored in IFE. Driver Irradiation Ignition Laser Direct Central hot spark Ignition HIB Indirect Fast ignition Impact ignition Pulse power Shock ignition The key issue of IFE is implosion physics which has progressed for more than 30 years Producing 1000times solid density and 108 degree temperature plasmas Plasma instabilities R Irradiation non-uniformities Thermal transport and ablation surface of fuel pellet ΔR R-M Instability ΔR0 R-T instability R0 R Feed through R-M and R-T Instabilities in deceleration phase Turbulent Mixing Canter of fuel pellet t Major Laser Fusion Facilities in the World NIF, LLNL, US. LMJ, CESTA, Bordeaux, France SG-III, Menyang,CAEP, China GXII-FIREX, ILE, Osaka, Japan OMEGA-EP, LLE, Rochester, US HiPER, RAL, UK Heavy Ion Beam Fusion: The advanced T-lean fusion fuel reactor Test Stand at LBNL NDCX-I US HIF Science Virtual National Lab.(LBNL, LLNL,PPPL) has been established in 1990. (Directed by G Logan) • Implosion physics by HIB • HIB accelerator technology for 1kA, 1GeV, 1mm2 beam: Beam brightness, Neutralization, NDCX II Collective effects of high current beam, Stripping.(R.Davidson etal) • Reactor concept with Flibe liquid jet wall (R.Moir: HYLIF for HIF Reactor) History of IFE Research 1960: Laser innovation (Maiman) 1972: Implosion concept (J.
    [Show full text]
  • Overview of Versatile Experiment Spherical Torus (VEST)
    Overview of Versatile Experiment Spherical Torus (VEST) Y.S. Hwang and VEST team March 29, 2017 CARFRE and CATS Dept. of Nuclear Engineering Seoul National University 23rd IAEA Technical MeetingExperimental on Researchresults and plans of Using VEST Small Fusion Devices, Santiago, Chille Outline Versatile Experiment Spherical Torus (VEST) . Device and discharge status Start-up experiments . Low loop voltage start-up using trapped particle configuration . EC/EBW heating for pre-ionization . DC helicity injection Studies for Advanced Tokamak . Research directions for high-beta and high-bootstrap STs . Preparation of long-pulse ohmic discharges . Preparation for heating and current drive systems . Preparation of profile diagnostics Long-term Research Plans Summary 1/36 VEST device and Machine status VEST device and Machine status 2/36 VEST (Versatile Experiment Spherical Torus) Objectives . Basic research on a compact, high- ST (Spherical Torus) with elongated chamber in partial solenoid configuration . Study on innovative start-up, non-inductive H&CD, high and innovative divertor concept, etc Specifications Present Future Toroidal B Field [T] 0.1 0.3 Major Radius [m] 0.45 0.4 Minor Radius [m] 0.33 0.3 Aspect Ratio >1.36 >1.33 Plasma Current [kA] ~100 kA 300 Elongation ~1.6 ~2 Safety factor, qa ~6 ~5 3/36 History of VEST Discharges • #2946: First plasma (Jan. 2013) • #10508: Hydrogen glow discharge cleaning (Nov. 2014) Ip of ~70 kA with duration of ~10 ms • #14945: Boronization with He GDC (Mar. 2016) Maximum Ip of ~100 kA • # ??:
    [Show full text]
  • LA-8700-C N O Proceedings of the Third Symposium on the Physics
    LA-8700-C n Conference Proceedings of the Third Symposium on the Physics and Technology of Compact Toroids in the Magnetic Fusion Energy Program Held at the Los Alamos National Laboratory Los Alamos, New Mexico December 2—4, 1980 c "(0 O a> 9 n& anna t LOS ALAMOS SCIENTIFIC LABORATORY Post Office Box 1663 Los Alamos. New Mexico 87545 An Affirmative Aution/f-qual Opportunity Fmployei This report was not edited by the Technical Information staff. This work was supported by the US Depart- ment of Energy, Office of Fusion Energy. DISCLAIM) R This report WJJ prepared as jn JLUOUIH of work sponsored by jn agency of ihc Untied Slates (.ovcrn- rneni Neither the United Suit's (iovci.iment nor anv a^cmy thereof, nor any HI theu employees, makes Jn> warranty, express or in,Hied, o( assumes any legal liability 01 responsibility for the jn-ur- aty. completeness, or usefulness of any information, apparatus, product, 01 process disiiosed, or rep- resents thai its use would not infringe privately owned rights. Reference herein to any specifu- com- mercial product process, or service by tradr name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommcniidlK>n, or favoring by the United Stales Government or any agency thereof. The views and opinions of authors expressed herein do not nec- essarily state 01 reflect those nf llic United Stales Government or any agency thereof. UfJITED STATES DEPARTMENT OF ENERGY CONTRACT W-7405-ENG. 36 LA-8700-C Conference UC-20 issued: March 1981 Proceedings of the Third Symposium on the Physics and Technology of Compact Toroids in the Magnetic Fusion Energy Program Heki at the Los Alamos National Laboratory Los Alamos, New Mexico Decamber 2—4, 1980 Compiled by Richard E.
    [Show full text]
  • Retarding Field Analyzer (RFA) for Use on EAST
    Magnetic Confinement Fusion C. Xiao and STOR-M team Plasma Physics Laboratory University of Saskatchewan Saskatoon, Canada \ Outline Magnetic Confinement scheme Progress in the world Tokamak Research at the University of Saskatchewan 2 CNS-2019 Fusion Session, June 24, 2019 Magnetic Confinement Scheme 3 CNS-2019 Fusion Session, June 24, 2019 Charged particle motion in straight magnetic field A charged particle circulates around the magnetic field lines (e.g., produced in a solenoid) Cross-field motion is restricted within Larmor radius 푚푣 푟 = 퐿 푞퐵 Motion along the field lines is still free End loss to the chamber wall Chamber Wall 4 CNS-2019 Fusion Session, June 24, 2019 Toriodal geometry is the solution However, plasma in simple toroidal field drifts to outboard on the wall 5 CNS-2019 Fusion Session, June 24, 2019 Tokamak Bend solenoid to form closed magnetic field lines circular field line without ends no end-loss. Transformer action produces a huge current in the chamber Generate poloidal field Heats the plasma Tokamak: abbreviation of Russian words for toroidal magnetic chamber 6 CNS-2019 Fusion Session, June 24, 2019 Stellarator • The magnetic field are generated by complicated external coils • No plasma current, no disruptions • Engineering is challenge 7 CNS-2019 Fusion Session, June 24, 2019 Wendelstein 7-X, Greifswald, Germany • Completed in October 2015 • Superconducting coils • High density and high temperature have been achieved 8 CNS-2019 Fusion Session, June 24, 2019 Reversed Field Pinch • Toroidal field reverses direction at the edge • The magnetic field are generated by current in plasma • Toroidal filed and poloidal field are of similar strength.
    [Show full text]