DOCSLIB.ORG

Comparison of Compact Toroid Configurations

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
Comparison of Compact Toroid Configurations UDC 533.9 COMPARISON OF COMPACT TOROID CONFIGURATIONS Paul M. Bellan (California Institute of Technology) and Thomas J. Dolan (IAEA) INTRODUCTION isolated spheromaks, but not the H mode or internal The IAEA Coordinated Research Project (CRP) barriers. Most of the transport barrier in spheromaks and on "Comparison of Compact Toroid Configurations" has FRC is near the separatrix. participants from Argentina, Brazil, China, India, Israel, Italy, Japan, Russia, Ukraine (Dr. Yaroslav FUELING AND EDGE PHYSICS ISSUES Kolesnichenko), UK, and USA. The results of a recent Edge physics studies have been done somewhat in CRP meeting are summarized here.1 Spherical tokamaks ST, but spheromaks and FRC have not been sustained (ST) have very low aspect ratios, which facilitates long enough for meaningful scrape off layers to develop. attainment of high b. Spheromaks have both poloidal and High power electrodes are used in ST for coaxial helicity toroidal fields, but no center post. 2 Field reversed injection and divertor biasing, and in spheromaks for configurations (FRC), have only poloidal magnetic plasma production. Tungsten alloy on copper substrate fields. looks good for some electrode applications, and is being tested in Proto-Sphera. H mode tokamaks, spheromaks, PLASMA FORMATION AND SUSTAINMENT and FRC all have difficulty with particle inventory Spherical tokamaks plasmas are usually control. Pellet injectors are useful for ST. The produced and sustained inductively. Spheromak plasmas spheromak community has developed high throughput gas are usually produced by coaxial guns or by inductive flux inlet valves, including hypersonic valves. Spheromaks and cores. Field reversed configurations have been produced FRC have not yet operated at pulse lengths that require by theta pinches, by merging two spheromaks with sustained fueling. Boronization may be a good technique opposite toroidal fields, and by rotating magnetic field for both spheromaks and FRC. Generally tokamaks run (RMF) current drive. ST, spheromaks, and FRC will all out of fuel, whereas spheromaks have too much. need some current sustainment by non-inductive means, such as electromagnetic waves, neutral beam injection ST EXPERIMENTS (NBI), or RMF. Parameters of National Spherical Torus Experiment (NSTX) (Princeton, USA) are: R = 0.85 m, EQUILIBRIUM, STABILITY, AND A = 1.3, k = 2.3, triangularity = 0.6, B = 0.3 T for 3 s, TRANSPORT f and If = 1 MA. The central column is insulated from the Typical beta values are 30% (ST), 10% remainder of the vacuum vessel to facilitate coaxial (spheromaks), and 70% (FRC). Flow shear has a helicity injection (CHI). There is also 6 MW of high stabilizing influence in ST. Plasma shaping, profile harmonic fast wave (30 MHz), and 5 MW of neutral control, and current drive have been done in ST, but not in beam injection (NBI) at 80 keV. NSTX has achieved 1 spheromaks or FRC. Spheromaks are nearly in the MA toroidal current, 130 kA toroidal current using CHI, “Taylor minimum energy” equilibrium, which is and performed initial experiments with high harmonic conducive to stability, and energetic beam ions are fast wave (HHFW) current drive, which showed expected to help stabilize them. Toroidal rotation is excessive plasma loading of the antenna. At I = 1 MA, V predicted to stabilize external kinks of ST, and to f ~ 3-5 V, b ~ 9%, and t ~ 25 ms. stabilize the tilt instability of spheromaks and FRC. Flow E The MegaAmp Spherical Tokamak (MAST) may also help to suppress the tilt instability of FRC. (Culham Laboratory, UK) has tested startup methods, The dangerous instabilities in ST are disruption, ballooning modes, kinks, neoclassical tearing modes, and demonstrated H-mode operation, and achieved If = 1 MA resistive wall modes. In spheromaks they are tilting and using neutral beam injection (NBI). The 1 MA toroidal relaxation events, and in FRC, tilting and rotational current was terminated abruptly by an internal reconnection event (IRE). Typical parameters are I f ~ 0.6 modes. The experimental stability of FRC exceeds that 19 -3 predicted theoretically. MA, n ~ 5x10 m , Te ~ 0.8 keV. Vertical plasma The H mode has been observed in ST, and motion control is essential to prevent machine damage. internal transport barriers are expected. Transport in ST The power loading measurements indicate that 80-90% is somewhat understood in terms of microturbulence of the power goes to the outboard strike point, which is suppression by magnetic shear and flow shear and desirable since the outboard strike point has much more surface area than the inner strike point. The wall power magnetic well. Transport in spheromaks is dominated by 2 the dynamo reconnection phenomena and should improve loading for a 0.5 MA plasma with no NBI is 1 MW/m , but with high-power NBI the loading will probably at higher Te. Transport in FRC is anomalous and not understood. Improved confinement is seen in decaying increase by a factor of ten. Problems of Atomic Science and Technology. 2000. N 3. Series: Plasma Physics (5). p. 81-83 81 The TST-2 spherical tokamak (University of the goal of obtaining 1 MA toroidal current for 3 ms. Tokyo, Japan) has design parameters of R = 0.36m, a = Experiments so far have shown that gettering reduces 0.23m, Bf = 0.4 T, If = 0.2 MA, FOH = 0.13 V-s. radiated power to less than 20% of total input power. A Parameters achieved so far are: Bf = 0.2 T, If = 0.09 MA, flat-top with 1.5 kG magnetic field has been achieved for tpulse = 0.02 s, Ti = 100 eV (O V measurement). Internal 1.8 ms. A multi-point Thomson scattering system and a Reconnection Events (IRE) have an abrupt increase in If, Transient Internal Probe (TIP) are being developed. The a decrease in Vloop, and a 40% density decrease. CORSICA code is being used to verify the plasma Magnetic probes show a consistent growth of a 10 kHz equilibrium by fitting surface magnetic probe perturbation and its harmonics. The RF system uses a measurements to a numerical prediction. A full 3D Faraday-shielded comb-line antenna designed to excite a numerical MHD calculation using the NIMROD code unidirectional HHFW. Low power (1 kW) RF shows evidence of Taylor relaxation and also evidence of propagation experiments performed so far indicate the doughhook mode seen previously on the SPHEX plasma loading of the antenna is much stronger than device at the University of Manchester. expected. The Berkeley Spheromak Experiment (Berkeley, 20 -3 The Globus M spherical tokamak (Ioffe CA, USA) has Bpol ~ 0.3 T, n ~ 2-7x10 m , and Te ~ 30- Institute, St. Petersburg, Russia) is in the start-up phase. 150 eV. It is investigating the application of 20 MW of Its current goals are to improve vacuum conditions 450 MHz lower hybrid heating via a slot in the flux (chamber baking at 200 C, glow discharge cleaning); to conserver. Diagnostics include Thomson scattering, a 3.8 study plasma-facing materials; and to install diagnostics meter ion Doppler spectrometer, a HeNe interferometer, including soft x-ray, impurity ion spectrometers, and magnetic probes. There is substantial MHD activity microwave interferometers. A toroidal current of 84 kA and the plasma decays after 100 ms. The device is fired was obtained with an associated loop voltage of 4V. The sufficiently fast that the electrodes become hot. The plasma duration of ~300 ms is limited by heat build-up. critical issue for lower hybrid waves is the accessibility The ETE spherical tokamak (Brazilian National condition for wave penetration, which requires waves Space Science Institute) is also in the start-up phase. It with very slow parallel phase velocity. will have A = 1.5, R0 = 0.3 m, B0 = 0.4 T, If = 0.2 MA, Unbounded spheromaks (California Institute of pulse length 10-15 ms, 7 kW ECH, 22 point Thomson Technology, USA) are formed in a large vacuum chamber scattering system, a 10 kV, 10-100 mA lithium beam and photographed using high speed cameras. Formation probe, and a submillimeter interferometer with added of spheromak configurations without a flux conserver HeNe laser to counteract vibration. contradicts conventional theory, which requires the The Sino-United Spherical Tokamak plasma to be bounded by a flux conserver. As with other (SUNIST) (Institute of Physics, the Chinese Academy of spheromak devices, the spheromaks were formed over a Sciences, and Tsinghua University) has: R = 0.3 m, A = distinct range of l, the ratio of gun current to gun bias 1.3, Bf = 0.15 T, and initial If = 50 kA. Plans include flux. Immediately after formation, the spheromaks wall pre-conditioning, ECRH startup studies, wave - convected away from the coaxial magnetized gun at a plasma interactions, and fast wave current drive, which constant velocity and expanded self-similarly. The should permit operation without OH coils. regime where l was marginally insufficient to form The Proto-Sphera spherical tokamak spheromaks produced distinctive helically twisted flux experiment (Frascati, Italy) will use a vertical plasma tubes. current Iz = 60 kA along the geometric axis, instead of a solid center post, to produce the toroidal magnetic field. FRC EXPERIMENTS Expected parameters are R = 0.35m, If = 120-240 kA, n The STX experiment (University of Washington, USA) 20 -3 = 10 m , Z = 2, T = 130 eV, tE = 2.3 ms. The cathode has demonstrated: (1) enhancement of the rotating current density will be 100 A/cm2. The machine is magnetic field (RMF) strength in the plasma relative to finished and cathode development experiments are the vacuum field strength, (2) initial penetration of the underway on a prototype screw pinch experiment, where RMF into the plasma on start-up and then exclusion to a 700 A flows axially in an external axial magnetic field surface layer as the plasma heats up, (3) a resistivity with Bz = 1.5 kG.
Load more

Recommended publications
  • 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]
  • Alternative Fusion Reactors As Future Commercial Power Plants
    J. Plasma Fusion Res. SERIES, Vol. 8 (2009) Alternative Fusion Reactors as Future Commercial Power Plants Sergei V. RYZHKOV Bauman Moscow State Technical University (Received: 29 August 2008 / Accepted: 1 April 2009) Alternative reactor based on a field-reversed configuration (FRC) has advantages of the cylindrical geometry, the open field line geometry (direct energy conversion (DEC) of the charged-particle flow), and high � (plasma pressure/magnetic-field pressure). This paper aims to evaluate the attractiveness of a low radioactive FRC fusion core. Analysis of a conceptual deuterium - helium-3 (D-3He) fusion power reactor is presented and reference point is defined. Principal parameters of the D-3He plasma reference case (RC) and comparison with conceptual D-3He tokamak and FRC power plants are shown. Keywords: advanced fuel, alternative concept, aneutronic reactions, bremsstrahlung, compact toroid, field reversed configuration, low radioactive reactor, magnetic confinement. 1. Introduction The main advantage of RMF is that as plasma The FRC [1,2] is a confinement device (FRC plasma shaping or ion beams RMF would be needed for stability. Various plasma parameters are given in [5] for RMF is a toroid with the exclusively poloidal magnetic field) combining of properties and prospects of the open and formed plasmas and theta-pinch formed plasmas. closed magnetic system and leading to very large reactor Appropriate hot, steady-state FRCs can now be formed using RMF and scaling laws developed for achievable advantages (see Fig. 1). Actually, FRC experiment was started in Russia (TRINITI) and USA (LANL) in 1970s. RMF sustained FRC flux levels [6]. Review papers have been published in the 1980s [3,4].
    [Show full text]
  • Formation of Hot, Stable, Long-Lived Field-Reversed Configuration Plasmas on the C-2W Device
    IOP Nuclear Fusion International Atomic Energy Agency Nuclear Fusion Nucl. Fusion Nucl. Fusion 59 (2019) 112009 (16pp) https://doi.org/10.1088/1741-4326/ab0be9 59 Formation of hot, stable, long-lived 2019 field-reversed configuration plasmas © 2019 IAEA, Vienna on the C-2W device NUFUAU H. Gota1 , M.W. Binderbauer1 , T. Tajima1, S. Putvinski1, M. Tuszewski1, 1 1 1 1 112009 B.H. Deng , S.A. Dettrick , D.K. Gupta , S. Korepanov , R.M. Magee1 , T. Roche1 , J.A. Romero1 , A. Smirnov1, V. Sokolov1, Y. Song1, L.C. Steinhauer1 , M.C. Thompson1 , E. Trask1 , A.D. Van H. Gota et al Drie1, X. Yang1, P. Yushmanov1, K. Zhai1 , I. Allfrey1, R. Andow1, E. Barraza1, M. Beall1 , N.G. Bolte1 , E. Bomgardner1, F. Ceccherini1, A. Chirumamilla1, R. Clary1, T. DeHaas1, J.D. Douglass1, A.M. DuBois1 , A. Dunaevsky1, D. Fallah1, P. Feng1, C. Finucane1, D.P. Fulton1, L. Galeotti1, K. Galvin1, E.M. Granstedt1 , M.E. Griswold1, U. Guerrero1, S. Gupta1, Printed in the UK K. Hubbard1, I. Isakov1, J.S. Kinley1, A. Korepanov1, S. Krause1, C.K. Lau1 , H. Leinweber1, J. Leuenberger1, D. Lieurance1, M. Madrid1, NF D. Madura1, T. Matsumoto1, V. Matvienko1, M. Meekins1, R. Mendoza1, R. Michel1, Y. Mok1, M. Morehouse1, M. Nations1 , A. Necas1, 1 1 1 1 1 10.1088/1741-4326/ab0be9 M. Onofri , D. Osin , A. Ottaviano , E. Parke , T.M. Schindler , J.H. Schroeder1, L. Sevier1, D. Sheftman1 , A. Sibley1, M. Signorelli1, R.J. Smith1 , M. Slepchenkov1, G. Snitchler1, J.B. Titus1, J. Ufnal1, Paper T. Valentine1, W. Waggoner1, J.K. Walters1, C.
    [Show full text]
  • Magnetic Levitation and Compression of Compact Tori
    Magnetic Levitation and Compression of Compact Tori Carl Dunlea1∗, Stephen Howard2, Wade Zawalski2, Kelly Epp2, Alex Mossman2, Chijin Xiao1, Akira Hirose1 1University of Saskatchewan, 116 Science Pl, Saskatoon, SK S7N 5E2, Canada 2General Fusion, 106 - 3680 Bonneville Pl, Burnaby, BC V3N 4T5, Canada ∗e-mail: [email protected] Abstract The magnetic compression experiment at General Fusion was a repetitive non-destructive test to study plasma physics to Magnetic Target Fusion compression. A compact torus (CT) is formed with a co-axial gun into a containment region with an hour-glass shaped inner flux conserver, and an insulating outer wall. External coil currents keep the CT off the outer wall (radial levitation) and then rapidly compress it inwards. The optimal external coil configuration greatly improved both the levitated CT lifetime and the rate of shots with good flux conservation during compression. As confirmed by spectrometer data, the improved levitation field profile reduced plasma impurity levels by suppressing the interaction between plasma and the insulating outer wall during the formation process. Significant increases in magnetic field, density, and ion temperature were routinely observed at magnetic compression despite the prevalence of an instability, thought be an external kink, at compression. Matching the decay rate of the levitation coil currents to that of the internal CT currents resulted in a reduced level of MHD activity associated with unintentional compression by the levitation field, and a higher probability of long-lived CTs. An axisymmetric finite element MHD code that conserves system energy, particle count, angular momentum, and toroidal flux, was developed to study CT formation into a levitation field and magnetic compression.
    [Show full text]
  • 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.
    [Show full text]
  • The Fork in the Road to Electric Power from Fusion General Fusion, Inc
    The Fork in the Road to Electric Power From Fusion General Fusion, Inc. Peter Lobner, 1 February 2021 General Fusion, Inc. was founded in 2002 in Vancouver, Canada by Michael Laberge. The firm is focusing on the development of a fusion power reactor based on magnetized target fusion (MTF) in a spherical, liquid metal liner implosion machine known as a “stabilized liner compressor” (SLC). Their website is here: https://generalfusion.com The General Fusion SLC reactor is comprised of a spherical reactor vessel, a magnetized target plasma injector known as a Coaxial Helicity Injection (CHI) Marshall gun, and an array of piston drivers on the outer surface of the vessel to mechanically compress and heat the target plasma to conditions needed for fusion. A key to this approach is that plasma lifetime must be long enough to allow for mechanical compression (several milliseconds). This factor led to General Fusion’s initial choice of spherical tokamak targets over field reversed configuration (FRC) and spheromak targets (tested on PI-1 and PI-2), which would have needed faster compression. General Fusion integrated large-scale prototype concept drawing. Source: adapted from General Fusion 1 The Fork in the Road to Electric Power From Fusion Inside the vessel, a rotating layer of flowing liquid metal forms the “stabilized liner” that establishes an evacuated cavity (a vortex cavity) along the centerline of the plasma compression chamber. The flowing liquid metal also serves as a “first wall” neutron blanket / radiation shield, a tritium breeding medium and a heat transfer medium. Details on how the vortex cavity is established inside the reactor vessel are provided in Patent CA2969934A1.
    [Show full text]
  • Peter O'shea, Michel Laberge, Mike Donaldson, Michael Delage General Fusion Inc., Burnaby, British Columbia, Canada APS DPP Conference San Jose, California Oct
    Acoustically Driven Magnetized Target Fusion at General Fusion: An Overview Peter O'Shea, Michel Laberge, Mike Donaldson, Michael Delage General Fusion Inc., Burnaby, British Columbia, Canada APS DPP Conference San Jose, California Oct. 31- Nov. 5, 2016 CP10.00103 INTRODUCTION THE CASE FOR MAGNETIZED TARGET FUSION (MTF) PLASMA TARGET DEVELOPMENT: SMALL INJECTORS SPHERICAL TOKAMAK DISCHARGES (Q>1) General Fusion’s Magnetized Target Fusion (MTF) concept involves Magnetized Target Fusion (MTF) seeks to operate at densities and time Several single-stage (formation only) plasma injectors have been Both PROSPECTOR and SPECTOR devices can produce spherical compressing an initial magnetically confined plasma (tE >100 msec) with a scales intermediate to those of ICF and Magnetized Fusion Energy (MFE) designed and tested at General Fusion. They have been built on a tokamak targets by forming plasma into a pre-existing toroidal field, 1000x volume compression in ~100 microseconds. If near adiabatic [Turchi]. MTF has much lower peak power than ICF and much lower reduced scale to reduce iteration time and expense and allow a variety of producing lifetimes up to 2 msec, and electron temperatures in excess of compression is achieved, the final plasma would produce reactor relevant stored energy than Magnetic confinement, allowing use of more geometries and overall safety factor (q) to be explored. Te ≥ 400eV (see General Fusion poster on Thomson Scattering in this fusion energy gain. (see initial and final plasma parameters below) economical technologies.
    [Show full text]
  • The Field-Reversed Configuration As a Practical Fusion Reactor Core
    The Field-Reversed Configuration (FRC) as a Practical Fusion Reactor Core Edward DeWit, Jordan Morelli Department of Physics, Engineering Physics, and Astronomy Queen’s University, Kingston, ON CAP Congress June 4, 2019 Outline Topics to be discussed • The case for fusion • Basic fusion physics • Basic FRC description • Brief history of FRC research • Technical benefits of the FRC • Results from TAE • Edge-biasing experiment • Summary and conclusion FIG: Conceptual drawing of the field-reversed configuration (FRC) 2 The case for fusion 3 The world needs energy Worst case Global energy consumption until 2100. Realistic scenario IIASA–WEC Study “Do nothing” “Global Energy Perspectives” Best case ≈ 2 × 4 Kikuchi, M., Lackner, K., and Tran, M. Q. (2012). Traditional sources of energy Fossil fuels are • In limited supply • Polluting • Geographically contested • Archaic 5 Traditional sources of energy (cont’d.) Solar and wind are • Intermittent • Low density 6 Traditional sources of energy (cont’d.) Nuclear fission is dangerous • Radioactive waste • Meltdown scenarios • Proliferation of weapons 7 Nuclear fusion Benefits of nuclear fusion • Energy dense • Unlimited, low cost fuel supply • No proliferation issues • No possibility of meltdown • No long-lived radioactive waste • Thermal or direct energy conversion options 8 Basic fusion physics 9 Fusion in the sun Proton-proton chain reaction 4 + 4푝 → 퐻푒 + 2푒 + 2휈푒 10 Fusion fuel 11 Kikuchi, M., Lackner, K., and Tran, M. Q. (2012). Main approaches to fusion on Earth https://www.iter.org/ https://lasers.llnl.gov/ Magnetic confinement fusion Inertial confinement fusion 12 Maxwell-Boltzmann and nuclear potential 13 Chen, F. F. Introduction to plasma physics and controlled fusion, volume 3.
    [Show full text]
  • P. O'shea, M. Laberge, M. Donaldson, M. Delage
    Magnetized Target Fusion At General Fusion: An Overview P. O'Shea, M. Laberge, M. Donaldson, M. Delage General Fusion Inc., Burnaby, British Columbia, Canada GF Original ACOUSTIC MTF Concept Plasma Target Development: Large Injector Plasma Target Development: Small Injectors Plasma Compression Tests (PCS program) General Fusion’s original Magnetized Target Fusion (MTF) concept involves General Fusion’s Pi1 and Pi2 systems further demonstrated compression Multiple plasma injectors have been designed and tested at General compressing an initial magnetically confined plasma (tE >100 msec) with a heating of a spheromak to over 300 eV and 3.2T magnetic fields. Fusion. They have been built on a reduced scale to reduce iteration time 1000x volume compression in ~100 microseconds. If near adiabatic Unfortunately, energy confinement of the CT at the end of the acceleration and expense and allow a variety of geometries and overall safety factor compression is achieved, the final plasma would produce reactor relevant section can be negatively impacted by high levels of residual pushing (q) to be explored. fusion energy gain. (see initial and final plasma parameters below) current. General Fusion’s newest large injector, Pi3, is designed to demonstrate ~30cm • Pistons kinetic energy: 120 MJ formation of a large spherical tokamak target suitable for use in a large scale • Initial plasma density: 1.25E23 m-3 magnetized target fusion prototype system, such as our upgraded concept. • Initial plasma temperature: 100 eV The technology may also have applications in solenoid-free startup in • Initial magnetic field: 7 Tesla steady-state spherical tokamak systems. • Initial plasma radius: 20 cm • Radial compression: 9.76 • Energy transfer to plasma: 14 MJ • Maximum fluid-plasma velocity: -2609 m/s • Peak plasma density: 1.16E26 m-3 • Peak plasma temperature: 24.6 keV All of the plasma results shown previously should be interpreted in the • Peak plasma pressure: 4.7 Mbar • Peak magnetic field: 665 Tesla context of General Fusion’s goal of developing an MTF power plant.
    [Show full text]
  • REVIEW of COMPACT, ALTERNATE CONCEPTS for MAGNETIC CONFINEMENT FUSION JUNE, 1984 REPORT NO: F8302g
    r.r THE CANADIAN FUSION FUEL TECHNOLOGY PROJECT REPRESENTS PART OF CANADA'S OVERALL EFFORT IN FUSION DEVELOPMENT. THE FOCUS FOR CFFTP IS TRITIUM AND TRITIUM TECHNOLOGY. THE PROJECT IS FUNDED BY THE GOVERNMENTS OF CANADA AND ONTARIO, AND BY THE UTILITY ONTARIO HYDRO; AND IS MANAGED BY ONTARIO HYDRO. CFFTP WILL SPONSOR RESEARCH, DEVELOPMENT, DESIGN AND ANALYSIS TO EXTEND EXISTING EXPERIENCE AND CAPABILITY GAINED IN HANDLING TRITIUM AS PART OF THE CANDU FISSION PROGRAM. IT IS PLANNED THAT THIS WORK WILL BE IN FULL COLLABORATION AND SERVE THE NEEDS OF INTERNATIONAL FUSION PROGRAMS. REVIEW OF COMPACT, ALTERNATE CONCEPTS FOR MAGNETIC CONFINEMENT FUSION JUNE 1984 REPORT NO: F84029 REVIEW OF COMPACT, ALTERNATE CONCEPTS FOR MAGNETIC CONFINEMENT FUSION JUNE, 1984 REPORT NO: F8302g Prepared by; S.B. Niokerson Engineering Physicist Ontario Hydro Research Division Reviewed by: D.P. Dautovich Manager - Technology Development Canadian Fusion Fuels Technology Project Approved by: T.S. Drolet Program Manager Canadian Fusion Fuels Technology Project LIST OF CONTRIBUTORS P.J. Dinner Reversed Field Pinches Canadian Fusion Fuels Technology Project S.B. Nickerson Compact Toroids Ontario Hydro Research Division High Power Density Tokamaks Spherical Pinch W.T. Shmayda Linear Magnetic Systems Ontario Hydro Research Division Miscellaneous Concepts P. Gierszewski Compact Mirrors Canadian Fusion Fuels Technology Project E.B. Deksnis Bumpy Toruses, Stellarators Canatom Inc. Torsatrons ACKNOWLEDGEMENT The study group wishes to acknowledge the contributions made by the various individuals that were visited during the study. The considerable amount of time invested by many of them in talking with us was extremely useful and is very much appreciated. The individuals visited were: R.A.
    [Show full text]
  • Ca9110926 ALTERNATE FUSION CONCEPTS
    ///////// •'•7//.' Canadian Fusion Fuels Technology Project ca9110926 ALTERNATE FUSION CONCEPTS: STATUS AND PLANS CFFTP-G-9009 October 1990 P.J. Gierszewski, A.A. Harms* and S.B. Nickerson' ALTERNATE FUSION CONCEPTS: STATUS AND PLANS CFFTP-G-9009 October 1990 P.J. Gierszewski, A.A. Harms* and S.B. Nickerson' McMaster University Ontario Hydro Research Division CFFTP-G-9009 Prepared by: P.J. GierszewskiO Fusion Systems Engineer Fuel Systems & Materials Development Canadian Fusion Fuels Technology Project Reviewed by: Manager Fuel Systems & Materials Development Canadian Fusion Fuels Technology Project Approved by: D.P. Dautovich Program Manager Canadian Fusion Fuels Technology Project ACKNOWLEDGEMENTS We are grateful to the research groups at Los Alamos National Laboratory CTR Division (HDZP, CPRF, ZT-40, FRX-C, CTX), Spectra Technologies (LSX), Naval Research Laboratory (ZFX), University of Maryland (MS), Oak Ridge National Laboratory (ATF), Imperial College (HZP), Institut Gas lonizzati (RFX) and University of Stuttgart (DPF), who showed us their facilities, clarified the key issues, and discussed their results and program plans. We also particularly wish to thank D. Rej (LANL), A. Robson (NRL), R. Krakowski (LANL), P. Stangeby (UTIAS), J. Linhart (U. Pisa), M. Peng (ORNL) and G. Miley (U. Illinois) who kindly reviewed specific sections of the report. ALTERNATE FUSION CONCEPTS STATUS AND PLANS Table of Contents 1. Introduction 1 2. Advanced Tokamaks 3 3. Stellarator 11 4. Spherical Torus 18 5. Reversed-Field Pinch 24 6. Dense Z-Pinch 32 7. Field-Reversed Configuration 38 8. Spheromak 45 9. Ignition Experiments and Reactors 9.1 Ignition 52 9.2 Reactors 53 Appendix A: Other Concepts 62 A.1 Colliding Beam Fusion (Migma) 62 A.2 Electrostatic Confinement 63 A.3 Muon-Catalyzed Fusion 64 A.4 Spherical Pinch 64 A.5 Dense Plasma Focus 65 A.6 Linear Systems 66 A.7 Miscellaneous Concepts 67 Appendix B: Inertial Confinement 75 1.
    [Show full text]
  • 2016 US-Japan Workshop on Compact Torus
    2016 US-Japan Workshop on Compact Torus “Equilibrium studies and novel applications of compact toroids based on innovative confinement techniques: The future of Compact Tori” August 22–24, 2016 at the Hotel Irvine Irvine, CaliFornia, USA Hosted by University oF CaliFornia, Irvine Organized by: Toshi Tajima (University of CaliFornia, Irvine – USA) Tomohiko Asai (Nihon University – Japan) 2016 US-Japan CT Workshop Dates: August 22–24, 2016 Venue: Hotel Irvine 17900 Jamboree Road Irvine, CaliFornia 92614, USA +1 (866) 396-4201 CT2016 Workshop Website: http://www.physics.uci.edu/US-JAPAN-CT2016/ General Contact: [email protected] Workshop Organizers: Toshi Tajima ([email protected]) Tomohiko Asai ([email protected]) Local Workshop Coordinators: Loren Steinhauer ([email protected]) Hiroshi Gota ([email protected]) Debbie Margarit ([email protected]) CT2016 Workshop Participants List Name (Last, First) Affiliation Country Asai, Tomohiko Nihon University Japan Bao, Jian University of California, Irvine USA Belova, Elena Princeton Plasma Physics Laboratory USA Binderbauer, Michl Tri Alpha Energy USA Cohen, Samuel Princeton Plasma Physics Laboratory USA Gota, Hiroshi Tri Alpha Energy USA Guttenfelder, Walter Princeton Plasma Physics Laboratory USA Haw, Magnus California Institute of Technology USA Horton, Wendell University of Texas at Austin USA Hossack, Aaron University of Washington USA Howard, Stephen General Fusion Canada Kaminou, Yasuhiro University of Tokyo Japan Kaur, Manjit Swarthmore College USA Kishimoto, Yasuaki
    [Show full text]