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The Fork in the Road to Electric Power from Fusion US Navy Compact
The Fork in the Road to Electric Power From Fusion US Navy compact fusion reactors Peter Lobner, 1 February 2021 1. Background For at least the past 40 years, the US Navy has been funding fusion power research and development in considerable secrecy. In this article, we’ll take a brief look at the following US Navy fusion programs, focusing on the two most recent programs. • LINUS - pulsed stabilized liquid liner compressor (SLC) • Low Energy Nuclear Reactions (LENR, aka cold fusion) • Polywell fusion - inertial electrostatic confinement (IEC) • NIKE & Electra krypton fluoride direct-drive laser inertial confinement fusion (ICF) • Plasma compression fusion device (2019) • Argon fluoride direct-drive laser ICF (2020) 2. LINUS - pulsed stabilized liquid liner compressor (SLC) In the 1970s, this Naval Research Laboratory (NRL)-sponsored project developed and tested several pulsed stabilized liquid liner compressor (SLC) machines: LINUS-0, SUZY-II and HELIUS. A plasma is injected into a void space in a flowing molten lead-lithium liner. The liquid liner is then imploded mechanically, using high- pressure helium-driven pistons. The imploding liner compresses and adiabatically heats the plasma to fusion conditions. While the SLC concept was abandoned by the US Navy in the 1970s, it was revived in the 2000s as the basis for the small fusion reactor designs being developed by Compact Fusion Systems (US) and General Fusion (Canada). 3. Low Energy Nuclear Reactions (LENR, aka cold fusion) From the mid 1990s to at least the mid-2000s the US Navy sponsored research into cold fusion. You’ll find a list of cold fusion papers by Navy researchers from NRL, China Lake Naval Weapons 1 The Fork in the Road to Electric Power From Fusion Laboratory, and Space and Naval Warfare Systems Center (SPAWAR) here: https://lenr-canr.org/wordpress/?page_id=952 4. -
Engineering Optimization of Stellarator Coils Lead to Improvements in Device Maintenance
2015 IEEE 26th Symposium on Fusion Engineering (SOFE 2015) Austin, Texas, USA 31 May – 4 June 2015 IEEE Catalog Number: CFP15SOF-POD ISBN: 978-1-4799-8265-3 Copyright © 2015 by the Institute of Electrical and Electronics Engineers, Inc All Rights Reserved Copyright and Reprint Permissions: Abstracting is permitted with credit to the source. Libraries are permitted to photocopy beyond the limit of U.S. copyright law for private use of patrons those articles in this volume that carry a code at the bottom of the first page, provided the per-copy fee indicated in the code is paid through Copyright Clearance Center, 222 Rosewood Drive, Danvers, MA 01923. For other copying, reprint or republication permission, write to IEEE Copyrights Manager, IEEE Service Center, 445 Hoes Lane, Piscataway, NJ 08854. All rights reserved. ***This publication is a representation of what appears in the IEEE Digital Libraries. Some format issues inherent in the e-media version may also appear in this print version. IEEE Catalog Number: CFP15SOF-POD ISBN (Print-On-Demand): 978-1-4799-8265-3 ISBN (Online): 978-1-4799-8264-6 ISSN: 1078-8891 Additional Copies of This Publication Are Available From: Curran Associates, Inc 57 Morehouse Lane Red Hook, NY 12571 USA Phone: (845) 758-0400 Fax: (845) 758-2633 E-mail: [email protected] Web: www.proceedings.com TABLE OF CONTENTS ENGINEERING OPTIMIZATION OF STELLARATOR COILS LEAD TO IMPROVEMENTS IN DEVICE MAINTENANCE ..................................................................................................................................................1 T. Brown, J. Breslau, D. Gates, N. Pomphrey, A. Zolfaghari NSTX TOROIDAL FIELD COIL TURN TO TURN SHORT DETECTION .................................................................7 S. Ramakrishnan, W. -
Inertial Electrostatic Confinement Fusor Cody Boyd Virginia Commonwealth University
Virginia Commonwealth University VCU Scholars Compass Capstone Design Expo Posters College of Engineering 2015 Inertial Electrostatic Confinement Fusor Cody Boyd Virginia Commonwealth University Brian Hortelano Virginia Commonwealth University Yonathan Kassaye Virginia Commonwealth University See next page for additional authors Follow this and additional works at: https://scholarscompass.vcu.edu/capstone Part of the Engineering Commons © The Author(s) Downloaded from https://scholarscompass.vcu.edu/capstone/40 This Poster is brought to you for free and open access by the College of Engineering at VCU Scholars Compass. It has been accepted for inclusion in Capstone Design Expo Posters by an authorized administrator of VCU Scholars Compass. For more information, please contact [email protected]. Authors Cody Boyd, Brian Hortelano, Yonathan Kassaye, Dimitris Killinger, Adam Stanfield, Jordan Stark, Thomas Veilleux, and Nick Reuter This poster is available at VCU Scholars Compass: https://scholarscompass.vcu.edu/capstone/40 Team Members: Cody Boyd, Brian Hortelano, Yonathan Kassaye, Dimitris Killinger, Adam Stanfield, Jordan Stark, Thomas Veilleux Inertial Electrostatic Faculty Advisor: Dr. Sama Bilbao Y Leon, Mr. James G. Miller Sponsor: Confinement Fusor Dominion Virginia Power What is Fusion? Shielding Computational Modeling Because the D-D fusion reaction One of the potential uses of the fusor will be to results in the production of neutrons irradiate materials and see how they behave after and X-rays, shielding is necessary to certain levels of both fast and thermal neutron protect users from the radiation exposure. To reduce the amount of time and produced by the fusor. A Monte Carlo resources spent testing, a computational model n-Particle (MCNP) model was using XOOPIC, a particle interaction software, developed to calculate the necessary was developed to model the fusor. -
Physique Nucléaire Et De L'instrumentation Associée Introduction
FR0108546 # DEA-DAPNIA-RA-1997-98 A il. ..33/04 -DSM Département d'Astrophysique, de physique des Particules, de physique Nucléaire et de l'Instrumentation Associée Introduction Motivés par la curiosité pour les connaissances fondamentales et soutenus par des investissements impor- tants, les chercheurs du vingtième siècle ont fait des découvertes scientifiques considérables, sources de retombées économiques fructueuses. Une recherche ambitieuse doit se poursuivre. Organisé pour déve- lopper les grands programmes pour le nucléaire et par le nucléaire, le CEA est bien armé pour concevoir et mettre au point les instruments destinés à explorer, en coopération avec les autres organismes de recherche, les confins de l'infiniment petit et ceux de l'infinimenf grand. La recherche fondamentale évolue et par essence ne doit pas avoir de frontières. Le Département d'astrophysique, de physique des particules, de physique nucléaire et de l'instrumentation associée (Dapnia) a été créé pour abolir les cloisons entre la physique nucléaire, la physique des particules et l'as- trophysique, tout en resserrant les liens entre physiciens, ingénieurs et techniciens au sein de la Direction des sciences de la matière (DSM). Le Dapnia est unique par sa pluridisciplinarité. Ce regroupement a permis de lancer des expériences se situant aux frontières de ces disciplines tout en favorisant de nou- velles orientations et les choix vers les programmes les plus prometteurs. Tout en bénéficiant de l'expertise d'autres départements du CEA, la recherche au Dapnia se fait princi- palement au sein de collaborations nationales et internationales. Les équipes du Dapnia, de I'IN2P3 (Institut national de physique nucléaire et de physique des particules) et de l'Insu (Institut national des sciences de l'Univers) se retrouvent dans de nombreuses grandes collaborations internationales, chacun apportant ses compétences spécifiques afin de renforcer l'impact de nos contributions. -
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. -
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. -
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. -
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. -
Time Evaluation of Diamagnetic Loop and Mirnov Oscillations in a Major Plasma Disruption and Comparison with a Normal Shot
International Nano Letters https://doi.org/10.1007/s40089-018-0259-x ORIGINAL ARTICLE Time evaluation of diamagnetic loop and Mirnov oscillations in a major plasma disruption and comparison with a normal shot R. Sadeghi1 · Mahmood Ghoranneviss1 · M. K. Salem1 Received: 21 November 2018 / Accepted: 7 December 2018 © The Author(s) 2018 Abstract In this paper, plasma disruption was investigated in IR-T1 tokamak. Moreover, the time evaluation of plasma parameters such as plasma current, Ip; loop voltage, Vloop; power heating; and safety factor was illustrated. The results of diamagnetic loop and Mirnov oscillations in a major disruption were compared with their results in a normal shot. In addition, plasma disruption in diferent tokamaks was investigated and the results were compared with the IR-T1 tokamak. Keywords Disruption · Runaway electrons · Mirnov coils · Diamagnetic loop · Tokamak · MHD instability Introduction tokamak disruptions cause plasma confinement to be destroyed by restriction of current and density which ends Among various tools of magnetic confnement, tokamak to large mechanical stresses. Plasma disruption is caused containing hot plasma is one of the best and developed by strong stochastic magnetic feld formed due to nonlin- devices [1]. Tokamaks are divided into two groups: frst, the earity excited low-mode number magneto–hydro–dynamics large tokamaks for studying large plasmas such as DIII-D (MHD) modes. The safety factor (q) is very important in [2] and Tore–Supra [3] with high-cost testing conditions and determining stability and transport theory [9–13]. The paper second, small tokamaks such as STOR-M [4] and ISTTOK is organized as follows: in Sect. -
Topical Review Solenoid-Free Plasma Start-Up in Spherical Tokamaks
Home Search Collections Journals About Contact us My IOPscience Solenoid-free plasma start-up in spherical tokamaks This content has been downloaded from IOPscience. Please scroll down to see the full text. 2014 Plasma Phys. Control. Fusion 56 103001 (http://iopscience.iop.org/0741-3335/56/10/103001) View the table of contents for this issue, or go to the journal homepage for more Download details: IP Address: 198.125.233.17 This content was downloaded on 06/01/2015 at 20:20 Please note that terms and conditions apply. Plasma Physics and Controlled Fusion Plasma Phys. Control. Fusion 56 (2014) 103001 (19pp) doi:10.1088/0741-3335/56/10/103001 Topical Review Solenoid-free plasma start-up in spherical tokamaks R Raman1 and V F Shevchenko2 1 William E. Boeing Department of Aeronautics and Astronautics, University of Washington, Seattle, WA 98195, USA 2 CCFE, Culham Science Centre, Abingdon, Oxon, OX14 3DB, UK E-mail: [email protected] Received 15 June 2014, revised 20 August 2014 Accepted for publication 1 September 2014 Published 22 September 2014 Abstract The central solenoid is an intrinsic part of all present-day tokamaks and most spherical tokamaks. The spherical torus (ST) confinement concept is projected to operate at high toroidal beta and at a high fraction of the non-inductive bootstrap current as required for an efficient reactor system. The use of a conventional solenoid in a ST-based fusion nuclear facility is generally believed to not be a possibility. Solenoid-free plasma start-up is therefore an area of extensive worldwide research activity. -
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 .