REVIEW of COMPACT, ALTERNATE CONCEPTS for MAGNETIC CONFINEMENT FUSION JUNE, 1984 REPORT NO: F8302g
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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 • # ??: -
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. -
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 . -
Fusion Space Propulsion-A Shorter Time Frame Than You Think
FusionFusion SpaceSpace Propulsion--Propulsion-- AA ShorterShorter TimeTime FrameFrame thanthan YouYou ThinkThink JohnJohn F.F. SantariusSantarius FusionFusion TechnologyTechnology InstituteInstitute UniversityUniversity ofof WisconsinWisconsin JANNAFJANNAF Monterey,Monterey, 5-85-8 DecemberDecember 20052005 D-3He and Pulsed-Power Fusion Approaches Would Shorten Development Times $$$ Fusion D-3HeD-3He FRC,FRC, dipole,dipole, Rocket spheromak,spheromak, ST;ST; Pulsed-powerPulsed-power MTF,MTF, PHD,PHD, fast-ignitorfast-ignitor JFS 2005 Fusion Technology Institute 2 D-3He Fusion Will Provide Capabilities Not Available from Other Propulsion Options 107 Fusion ) s 6 / 10 10 kW/kg m ( y 1 kW/kg t i c o l 5 0.1 kW/kg e 10 v t Nuclear us (fission) Ga s-core fission ha electric x 4 E 10 Nuclear thermal Chemical 103 10-5 10-4 10-3 10-2 10-1 1 10 Thrust-to-weight ratio JFS 2005 Fusion Technology Institute 3 Predicted Specific Power of D-3He Magnetic Fusion Rockets Is Attractive (>1 kW/kg) • Predictions based on reasonably detailed magnetic fusion rocket studies. Specific Power First Author Year Configuration (kW/kg) Borowski 1987 Spheromak 10.5 Borowski 1987 Spherical torus 5.8 Santarius 1988 Tandem mirror 1.2 Bussard 1990 Riggatron 3.9 Teller 1991 Dipole 1.0 Nakashima 1994 Field-reversed configuration 1.0 Emrich 2000 Gasdynamic mirror 130 Thio 2002 Magnetized-target fusion 50 Williams 2003 Spherical torus 8.7 Cheung 2004 Colliding-beam FRC 1.5 JFS 2005 Fusion Technology Institute 4 Fusion Propulsion Would Enable Fast and Efficient Solar-System Travel • Fusion propulsion would dramatically reduce trip times (shown below) or increase payload fractions. -
Years of Fusion Research
“50” Years of Fusion Research Dale Meade Fusion Innovation Research and Energy® Princeton, NJ Independent Activities Period (IAP) January 19, 2011 MIT PSFC Cambridge, MA 02139 1 FiFusion Fi FiPre Powers th thSe Sun “We nee d to see if we can mak e f usi on work .” John Holdren @MIT, April, 2009 3 Toroidal Magg(netic Confinement (1940s-earlyy) 50s) • 1940s - first ideas on using a magnetic field to confine a hot plasma for fusion. • 1947 Sir G.P. Thomson and P. C. Thonemann began classified investigations of toroidal “pinch” RF discharge, eventually lead to ZETA, a large pinch at Harwell, England 1956. • 1949 Richter in Argentina issues Press Release proclaiming fusion, turns out to be bogus, but news piques Spitzer’s interest. • 1950 Spitzer conceives stellarator while on a ski lift, and makes ppproposal to AEC ($50k )-initiates Project Matterhorn at Princeton. • 1950s Classified US Program on Controlled Thermonuclear Fusion (Project Sherwood) carried out until 1958 when magnetic fusion research was declassified. US and others unveil results at 2nd UN Atoms for Peace Conference in Geneva 1958. Fusion Leading to 1958 Geneva Meeting • A period of rapid progress in science and technology – N-weapons, N-submarine, Fission energy, Sputnik, transistor, .... • Controlled Thermonuclear Fusion had great potential – Much optimism in the early 1950s with expectation for a quick solution – Political support and pressure for quick results (but bud gets were low, $56M for 1951-1958) – Many very “innovative” approaches were put forward. – Early fusion reactor concepts - Tamm/Sakharov, Spitzer (Model D) very large. • Reality began to set in by the mid 1950s – Coll ectiv e eff ects - MHD instability ( 195 4), Bo hm d iffus io n was ubi qui tous – Meager plasma physics understanding led to trial and error approaches – A multitude of experiments were tried and ended up far from fusion conditions – Magnetic Fusion research in the U.S. -
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 -
Information Center Is to Provide Broadest Dissemination Possi
A major purpose of the Techni- cal Information Center is to provide the broadest dissemination possi- Me of information contained in DOE’s Research and Development Reports to business, industry, the academic community, and federal, state and local governments. Although a small portion of this report is not reproducible, it is being made available to expedite the availability of information on the research discussed herein. LA-UR -83-930 NOTICE PORTIONS fl~ T!+:3 l?EPi)RT .RI!E !!.LEG18LE. TITLE COMPACT FUS ION REACTORS ———_ . _ It has kk’i: r:~roduccd ?rom the best availoblc copy to permit !he hroadeti P0SSihJ8 avallabJJJtg AuTPIoa[s) R. A. tiraho~skl Los Alamos National Laboratory, Los Alamos, !1!1S7545 R, L. liil~(211SOll ‘1’cchnologv International Inc. , Ames, Iowa 500i9 MASTER SUB~IfTED TO 5th ANS Tupical Mcctini! on the Technnlokv of I%sif}n Hncrjv Knoxville, T:/ (April ‘26-2N, 1983) “l-hisrcporlwasprcpmcdusm ucimuntdwork spuniurcdhyxnMKcncyur[hc[JnimdSIaIa (iuvcrmncn{.Neithcrihc(JnilcdSlohx+(iuvcrnmcntII,)rtinyngcncylhcrw(,nurnnyorlhcir cmplnyw.nmkcsunywnrran[y,caprcmurim])licd,m nmumcsunyIcguliinhllilyurrccpunai. hilityIurtheuccurncy,cumplclcncm.nrusrfulnckso(tinyinkwmuliun,qqwrnius,prducl,nr prucxMdiccluscd,orrcp-nlsthutilsutcwIIuldnulinfrin~cprivatelyuwncdrights.Ncfcr. CIILZhereinlounyqwci[iccommcrciulprmluct,prwxc,urservicehytraocname,Irudcmurk, mrinuructurcr,orotherwiseIJ(RMnwincucxmrilyamti[i[utcorimplyihcndurwmenl,rccwm. mcrrdnllun,or(nvuringhy the[Jni~cdStuIcK(invcrnmcnlw UIIVngcrwyIhqrcur.llc vlcwa nmlnpiniomd uuilw+cqwcmcdhcrclntlunotncwcurilyMIMIC.w -
Fusion Rockets for Planetary Defense
| Los Alamos National Laboratory | Fusion Rockets for Planetary Defense Glen Wurden Los Alamos National Laboratory PPPL Colloquium March 16, 2016 LA-UR-16-21396 LA-UR-15-xxxx UNCLASSIFIED Operated by Los Alamos National Security, LLC for the U.S. Department of Energy's NNSA | Los Alamos National Laboratory | My collaborators on this topic: T. E. Weber1, P. J. Turchi2, P. B. Parks3, T. E. Evans3, S. A. Cohen4, J. T. Cassibry5, E. M. Campbell6 . 1Los Alamos National Laboratory . 2Santa Fe, NM . 3General Atomics . 4Princeton Plasma Physics Laboratory . 5University of Alabama, Huntsville . 6LLE, University of Rochester, Rochester Wurden et al., Journal of Fusion Energy, Vol. 35, 1, 123 (2016) UNCLASSIFIED Operated by Los Alamos National Security, LLC for the U.S. Department of Energy's NNSA | Los Alamos National Laboratory | How many ways is electricity made today? Primary Energy Source Nominally CO2 Free Current capacity (%) Expected Lifetime (yrs) Natural Gas no 100 Coal no 80.6 400 Oil no < 50 Biomass neutral 11.4 > 400 Wind yes 0.5 > 1000 Solar photovoltaic yes 0.06 > 1000 Solar thermal yes 0.17 > 1000 Hydro yes 3.3 > 1000 Wave/Tidal yes 0.001 > 1000 Geothermal yes 0.12 > 1000 Nuclear fission yes 2.7 > 400 [i] REN21–Renewable Energy Policy Network for the 21st Century Renewables 2012–Global Status Report, 2012, http://www.map.ren21.net/GSR/GSR2012.pdf , http://en.wikipedia.org/wiki/Energy_development UNCLASSIFIED Operated by Los Alamos National Security, LLC for the U.S. Department of Energy's NNSA | Los Alamos National Laboratory | What is the most important product that fusion could deliver? . -
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. -
(!Ss%LOSALAMOS SCIENTIFIC LABORATORY
LA-UR-8”-J020° TITLE: A RZL’IEW OF A1.’f’Ek?JATIl’E CO SC KPTS FI~!l F!AC SET1(: Fl:SIf)N AUTHOR(S): R. A. Kri~kowskl, R. 1,. hflllt’r iln(l R. 1.. tlil~~l~+’n SUBMllTED TO: 4~11ANST1’p[~sillylt,~.tIn}; (JII t]]e Ttrhnrrl[)Kv l~f Contr[)llcd !fuclmr l:IISiIIn KIIIK of l’rus~!il, PA (ocLOl)Cr ]4’+-]7, 1980) —— — IMICLAIMIU——— By 8ceptana of this arllclo, the publlshcr rcco~nimt that tfw U.S. Oowrnmnt rmdm anoncrnclusiw, rovalty. frw Ilanw 10 publish or r@produa the publlt~d form of thiscontribu. tkn, Or 10 OllOW othcft to do SO, for U.S. Goverrwwnt pur. fmsm, Tho LoI Almas SciwIIlfic Labormow mqutbtithatth~pub. Ihfmr idantlfi this wtlclcm work pcrfornwd unriw tfw ● m. pICCS Of t~ U.S. Mpanmnt of Enargy, (!ss%LOS ALAMOS SCIENTIFIC LABORATORY Post Office Box 1663 Los Alamos, New Mexico 87545 An AfflrrnatfveAction/Equal Opportunity Porm No, &la R3 8t. No. 2820 12/70 . ..... ----- . ,, ,, ● * . Rohcrt A. Kr.lkowski, RJ)II.11,1 L. Hiller and Ran(iv 1.. Ikgrnsori Los AJacrns .%lentlflr !,ahor.~tory, l!nlvrrxlry of C~llternla LnM AlamoK, NM H75A5 ,, —. -.. .- .,. .- . -. All:’ wtli momL certdlnly Cvl)lvc am Innig)li’ ‘ of t ho ~rld”s quest :or EIANIIVIIc fusion power, dcvrlopa from expvrlment, thvory ●nd ayntemn with the tandem mirrnr serving an a primary studies. backup Cone.?pt in the US fus loll prukfrnm, ● wide Il:c awnrmlry of the AFC’rI give II cm Tablv I rnng,, of alternative fuu ion cooccpts (Ak L’o) have ha$ treon org.lnittid inLo rhv following c.itogorlo~: bevn an,! nru bring pursurd.