The Fork in the Road to Electric Power from Fusion General Fusion, Inc
Total Page:16
File Type:pdf, Size:1020Kb
Load more
Recommended publications
-
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……………………………………………………. -
Spherical Tokamak) on the Path to Fusion Energy
Spherical Torus (Spherical Tokamak) on the Path to Fusion Energy ST can support fast implementation of fusion Demo in unique, important ways 1) Opportunities to support the strategy of Demo after ITER 2) Important ways in which ST can do so 3) Component Test Facility for steady state integrated testing 4) Broad progress and the remaining CTF physics R&D needs Martin Peng, NSTX Program Director Fusion Power Associates Annual Meeting and Symposium Fusion: Pathway to the Future September 27-28, 2006, Washington D.C. EU-Japan plan of Broader Approach toward Demo introduces opportunities in physics and component EVEDA OAK RIDGE NATIONAL LABORATORY S. Matsuda, SOFT 2006 U. S. DEPARTMENT OF ENERGY FPA Annual Mtg & Symp, 09/27-28/2006 2 Korean fusion energy development plan introduces opportunities in accelerating fusion technology R&D OAK RIDGEGS NATIONAL Lee, US LABORATORY2006 U. S. DEPARTMENT OF ENERGY FPA Annual Mtg & Symp, 09/27-28/2006 3 We propose that ST research addresses issues in support of this strategy • Support and benefit from USBPO-ITPA activities in preparation for burning plasma research in ITER using physics breadth provided by ST. • Complement and extend tokamak physics experiments, by maximizing synergy in investigating key scientific issues of tokamak fusion plasmas • Enable attractive integrated Component Test Facility (CTF) to support Demo, by NSTX establishing ST database and example leveraging the advancing tokamak database for ITER burning plasma operation and control. ST (All) USBPO- ITPA (~2/5) Tokamak (~3/4) OAK RIDGE NATIONAL LABORATORY U. S. DEPARTMENT OF ENERGY FPA Annual Mtg & Symp, 09/27-28/2006 4 World Spherical Tokamak research has expanded to 22 experiments addressing key physics issues MAST (UK) NSTX (US) OAK RIDGE NATIONAL LABORATORY U. -
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. -
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]. -
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. -
MHD in the Spherical Tokamak
21 st IAEA Fusion Energy Conference, Chengdu, China, 2006 MHD in the Spherical Tokamak MAST authors: SD Pinches , I Chapman, MP Gryaznevich, DF Howell, SE Sharapov, RJ Akers, LC Appel, RJ Buttery, NJ Conway, G Cunningham, TC Hender, GTA Huysmans, EX/7-2Ra R Martin and the MAST and NBI Teams NSTX authors: A.C. Sontag, S.A. Sabbagh, W. Zhu, J.E. Menard, R.E. Bell, J.M. Bialek, M.G. Bell, D.A. Gates, A.H. Glasser, B.P. Leblanc, F.M. Levinton, K.C. Shaing, D. Stutman, K.L. Tritz, H. Yu, and the NSTX Research Team EX/7-2Rb Office of Supported by Science This work was jointly funded by the UK Engineering & Physical Sciences Research Council and Euratom MHD physics understanding to reduce performance risks in ITER and a CTF – Error field studies – RWM stability in high beta plasmas – Effects of rotation upon sawteeth – Alfvén cascades in reversed shear EX/7-2Ra EX/7-2Rb Error field studies in MAST EX/7-2Ra Error fields: slow rotation, induce instabilities, terminate discharge Mega Ampere Spherical Tokamak R = 0.85m, R/a ~ 1.3 Four ex-vessel (ITER-like) error field correction coils wired to produce odd-n spectrum, Imax = 15 kA·turns (3 turns) Locked mode scaling in MAST EX/7-2Ra Error fields contribute to βN limit: n=1 kink B21 is the m = 2, n = 1 field component normal to q = 2 surface: • Similar density scaling observed on NSTX • Extrapolating to a Spherical Tokamak Power Plant / Component Test Facility gives locked mode thresholds ≈ intrinsic error ⇒ prudent to include EFCCs [Howell et al . -
Discussion Paper DIS-16-04 Small Modular Reactors: Regulatory
Discussion Paper DIS-16-04 Small Modular Reactors: Regulatory Strategy, Approaches and Challenges Section 3. Fusion Technologies CNSC would like to know: 1. What are the types and magnitudes of risks and hazards that would be posed by different fusion technologies (conventional and radiation hazards)? 2. With this in mind, how would the risks posed by activities involving fusion reactors differ from current nuclear fission reactors? 3. Should fusion reactors be regulated differently than fission reactors? 1. Risks and hazards posed by different fusion technologies Summary Response Fusion facilities, both research and development stage, and future commercial power producing systems, will have radiation hazards driven by three factors: • Inventory of volatile radioactive substances, primarily tritium • Prompt exposure to neutron or high energy photon flux from a fusion reaction • Radioactivity from decay of materials activated by fusion neutron flux The magnitudes of these radiation hazards will depend on the specific fusion technology and the nature of the system. Large volume magnetic fusion systems, for example, may have higher tritium inventories than pulsed approaches. Similarly, neutron and photon energy flux will depend on the design of blanket and shielding systems that may be technology specific. While total tritium inventory at any one time is unlikely to create a high accidental release risk to the public, total annual tritium throughput in a fusion power plant will be relatively high (a 500 MWt fusion plant will need to produce and consume ~30 kg of tritium per year). The management and containment of tritium flows during regular operation is therefore likely to be the most important area of interest for regulators. -
22.615, MHD Theory of Fusion Systems Prof. Freidberg Lecture #14: Real Tokamaks (With Bob Granetz)
22.615, MHD Theory of Fusion Systems Prof. Freidberg Lecture #14: Real Tokamaks (with Bob Granetz) 1. Today’s lecture presents a qualitative picture of various members of the tokamak family. These include: a. Ohmic tokamak - discussed in class b. High E tokamak - discussed in class (ITER) c. Advanced tokamak (AT operation – not so hot) d. Reversed shear tokamak (RS operation – good AT operation) e. Spherical tokamak (NSTX, MAST) 2. It will also include a discussion of the MHD behavior of Alcator C-Mod presented by Dr. Bob Granetz. 3. We begin with a brief discussion of elongation and why it is good as well as a short summary of the main instabilities of interest. These instabilities are discussed in more detail during the second part of the term. 4. Elongation – from an MHD point of view, elongation is desirable because it allows higher current I and higher E without sacrificing stability. High I also improves transport: WvI . 5. Recall that q* 1/I so that increasing I tends to decrease qa, therby decreasing stability. Elongation can compensate this effect. 6. The idea is as follows. If we assume that stability depends upon the value of q* or q,a regardless of plasma shape, then we can show that elongation allows higher I without changing q. 7. The assumption that stability depends largely on q* turns out to be approximately true for current driven kinks (that lead to disruption). Also, elongation uses the critical E for stability for a fixed q. 8. Let us determine an approximate relation between q, I, and elongation N . -
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. -
Media Kit 2015 Fusion Quick Facts
MEDIA KIT 2015 FUSION QUICK FACTS FUSION IS A GAME CHANGER It has the potential to handle the world’s future energy demands, cleanly, safely and inexpensively. FUSION ENERGY IS CLEAN Fusion will generate no greenhouse gases that produce climate change. Compare that to coal, which sends 1000 kilograms of greenhouse gas carbon dioxide into the atmosphere for every megawatt hour of electricity produced. Coal is still responsible for supplying 40% of the world’s electricity. FUSION IS CLOSER THAN YOU THINK Since the 1970s, progress in fusion energy has been moving at a pace similar to Moore’s Law – which states that computer processing power doubles every two years. Around the world, countries are launching programs to design the first demonstration fusion power plants. THE FUSION FUEL SUPPLY IS UNLIMITED Fusion is powered by deuterium and tritium. Deuterium is an isotope of hydrogen found in the oceans, and tritium is made in a fusion power plant from abundant lithium. Deuterium and lithium resources on earth could supply the world with energy for hundreds of millions of years. • Lithium is the earth’s 25th most abundant element. The total lithium content of seawater is very large and is estimated as 230 billion tonnes. Concerns regarding lithium availability for hybrid or electric vehicle batteries or other foreseeable applications are unfounded. FUSION IS NOT YOUR FATHER’S NUCLEAR POWER Compared to nuclear power, fusion is safe: • Fusion power plants cannot melt down. • A fusion plant would produce no long-lived radioactive material; at any given time it would contain only about as much radioactivity as a cancer radiation treatment machine. -
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. -
Compact Fusion Reactors
Compact fusion reactors Tomas Lind´en Helsinki Institute of Physics 26.03.2015 Fusion research is currently to a large extent focused on tokamak (ITER) and inertial confinement (NIF) research. In addition to these large international or national efforts there are private companies performing fusion research using much smaller devices than ITER or NIF. The attempt to achieve fusion energy production through relatively small and compact devices compared to tokamaks decreases the costs and building time of the reactors and this has allowed some private companies to enter the field, like EMC2, General Fusion, Helion Energy, Lockheed Martin and LPP Fusion. Some of these companies are trying to demonstrate net energy production within the next few years. If they are successful their next step is to attempt to commercialize their technology. In this presentation an overview of compact fusion reactor concepts is given. CERN Colloquium 26th of March 2015 Tomas Lind´en (HIP) Compact fusion reactors 26.03.2015 1 / 37 Contents Contents 1 Introduction 2 Funding of fusion research 3 Basics of fusion 4 The Polywell reactor 5 Lockheed Martin CFR 6 Dense plasma focus 7 MTF 8 Other fusion concepts or companies 9 Summary Tomas Lind´en (HIP) Compact fusion reactors 26.03.2015 2 / 37 Introduction Introduction Climate disruption ! ! Pollution ! ! ! Extinctions Ecosystem Transformation Population growth and consumption There is no silver bullet to solve these issues, but energy production is "#$%&'$($#!)*&+%&+,+!*&!! central to many of these issues. -.$&'.$&$&/!0,1.&$'23+! Economically practical fusion power 4$(%!",55*6'!"2+'%1+!$&! could contribute significantly to meet +' '7%!89 !)%&',62! the future increased energy :&(*61.'$*&!(*6!;*<$#2!-.=%6+! production demands in a sustainable way.