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The Next Generation of Fusion Energy Research
THE NEXT GENERATION OF FUSION ENERGY RESEARCH HEARING BEFORE THE SUBCOMMITTEE ON ENERGY AND ENVIRONMENT COMMITTEE ON SCIENCE AND TECHNOLOGY HOUSE OF REPRESENTATIVES ONE HUNDRED ELEVENTH CONGRESS FIRST SESSION OCTOBER 29, 2009 Serial No. 111–61 Printed for the use of the Committee on Science and Technology ( Available via the World Wide Web: http://www.science.house.gov U.S. GOVERNMENT PRINTING OFFICE 52–894PDF WASHINGTON : 2010 For sale by the Superintendent of Documents, U.S. Government Printing Office Internet: bookstore.gpo.gov Phone: toll free (866) 512–1800; DC area (202) 512–1800 Fax: (202) 512–2104 Mail: Stop IDCC, Washington, DC 20402–0001 COMMITTEE ON SCIENCE AND TECHNOLOGY HON. BART GORDON, Tennessee, Chair JERRY F. COSTELLO, Illinois RALPH M. HALL, Texas EDDIE BERNICE JOHNSON, Texas F. JAMES SENSENBRENNER JR., LYNN C. WOOLSEY, California Wisconsin DAVID WU, Oregon LAMAR S. SMITH, Texas BRIAN BAIRD, Washington DANA ROHRABACHER, California BRAD MILLER, North Carolina ROSCOE G. BARTLETT, Maryland DANIEL LIPINSKI, Illinois VERNON J. EHLERS, Michigan GABRIELLE GIFFORDS, Arizona FRANK D. LUCAS, Oklahoma DONNA F. EDWARDS, Maryland JUDY BIGGERT, Illinois MARCIA L. FUDGE, Ohio W. TODD AKIN, Missouri BEN R. LUJA´ N, New Mexico RANDY NEUGEBAUER, Texas PAUL D. TONKO, New York BOB INGLIS, South Carolina PARKER GRIFFITH, Alabama MICHAEL T. MCCAUL, Texas STEVEN R. ROTHMAN, New Jersey MARIO DIAZ-BALART, Florida JIM MATHESON, Utah BRIAN P. BILBRAY, California LINCOLN DAVIS, Tennessee ADRIAN SMITH, Nebraska BEN CHANDLER, Kentucky PAUL C. BROUN, Georgia RUSS CARNAHAN, Missouri PETE OLSON, Texas BARON P. HILL, Indiana HARRY E. MITCHELL, Arizona CHARLES A. WILSON, Ohio KATHLEEN DAHLKEMPER, Pennsylvania ALAN GRAYSON, Florida SUZANNE M. -
Historical Perspective on the United States Fusion Program
Historical Perspective on the United States Fusion Program Invited paper presented at American Nuclear Society 16th Topical Meeting on the Technology of Fusion Energy 14-16 September, 2004 in Madison, WI Stephen O. Dean Fusion Power Associates, 2 Professional Drive, Suite 249, Gaithersburg, MD 20879 [email protected] A variety of methods to heat the nuclei to the Progress and Policy is traced over the approximately high speeds (kinetic energies) required to penetrate the 55 year history of the U. S. Fusion Program. The Coulomb barrier have been successfully utilized, classified beginnings of the effort in the 1950s ended with including running a high current through an ionized declassification in 1958. The effort struggled during the hydrogen gas ("ohmic heating"), accelerating beams of 1960s, but ended on a positive note with the emergence of nuclei, and using radio-frequency power. Temperatures the tokamak and the promise of laser fusion. The decade well in excess of the 50 million degrees needed for fusion of the 1970s was the “Golden Age” of fusion, with large are now routinely achieved. budget increases and the construction of many new facilities, including the Tokamak Fusion Test Reactor II. THE 1960s AND 1970s (TFTR) and the Shiva laser. The decade ended on a high note with the passage of the Magnetic Fusion Energy During the decade of the 1960s, and continuing Engineering Act of 1980, overwhelming approved by to the present, scientists developed a whole new branch of Congress and signed by President Carter. The Act called physics, called plasma physics [3], to describe the for a “$20 billion, 20-year” effort aimed at construction behavior of these plasmas in various magnetic of a fusion Demonstration Power Plant around the end of configurations, and sophisticated theories, models and the century. -
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. -
Environmental Impact Statement and Environmental Impact Report for Continued Operation of Lawrence Livermore National Laboratory and Sandia National Labo
Environmental Impact Statement and Environmental Impact Report for Continued Operation of Lawrence Livermore National Laboratory and Sandia National Labo... APPENDIX A DESCRIPTION OF MAJOR PROGRAMS AND FACILITIES Appendix A describes the programs, infrastructures, facilities, and future plans of Lawrence Livermore National Laboratory (LLNL) and the Sandia National Laboratories at Livermore (SNL, Livermore). It provides information on existing activities and facilities, as well as information on those activities anticipated to occur or facilities to be constructed over the next 5 to 10 years. The purpose of this appendix is to: present information that can be used to evaluate the proposed action and other EIS/EIR alternatives, identify activities that are part of the proposed action, distinguish proposed action activities from no action alternative activities, and provide supporting documentation for less detailed descriptions of these activities or facilities found in other sections and appendices of the EIS/EIR. Figure A-1 illustrates how this appendix interfaces with other sections and appendices of this EIS/EIR. Most LLNL and all SNL, Livermore operations are located at sites near Livermore, California. LLNL also operates LLNL Site 300 near Tracy, California, and conducts limited activities at several leased properties near the LLNL Livermore site, as well as in leased offices in Los Angeles, California, and Germantown, Maryland. Figure A-2 and Figure A-3 show the regional location of the LLNL Livermore site, LLNL Site 300, and SNL, Livermore and their location with respect to the cities of Livermore and Tracy. While they are distinct operations managed and operated by different contractors, for purposes of this document LLNL Livermore and SNL, Livermore sites are addressed together because of their proximity. -
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. -
Direct-Drive Shock-Ignition for the Laser Megajoule
Direct-Drive Shock-Ignition for the Laser Megajoule. B. Canaud∗, S. Laffite, V. Brandon CEA, DAM, DIF, F-91297 Arpajon, France M. Temporal, R. Ramis ETSIA, Universidad Politecnica de Madrid, Spain (Dated: October 13, 2011) We present a review of direct-drive shock ignition studies done as alternative for the Laser Mega- Joule to achieve high thermonuclear gain. One-dimensional analysis of HiPER-like Shock-ignited target designs is presented. It is shown that high gain can be achieved with shock ignition for designs which do not ignite only from the laser compression. Shock ignition is achieved for different targets of the fast ignition family which are driven by an absorbed energy between 100 kJ and 850 kJ and deliver thermonuclear energies between 10-130 MJ. Shock-Ignition of Direct-Drive Double- Shell non-cryogenic target is also addressed. 2D results concerning the LMJ irradiation geometry are presented. Few systematic analyses are performed for the fuel assembly irradiation uniformity using the whole LMJ configuration or a part of the facility, and for the ignitor spike uniformity. Solutions for fuel assembly and shock ignition on LMJ using 2D calculations are presented. It is shown that high-gain shock-ignition is possible with intensity of each quad less than 1e15 W/cm2 but low modes asymmetries displace the ignitor power in the spike towards higher powers.. PACS numbers: 52.57.Bc, 52.57.-z,52.35.Tc,52.57.Kk I. INTRODUCTION Direct drive inertial fusion is an alternative to achieve inertial confinement fusion for the laser Megajoule (LMJ) for a decade [1{7]. -
ITER • NCSX • HEDLP Joint Program • Issues and Plans
U.S. Department of Energy’s Office of Science Fusion Energy Sciences Program Update Fusion Energy Sciences Advisory Committee Gaithersburg, MD October 23-24, 2007 Raymond J. Fonck Associate Director for Fusion Energy Sciences www.ofes.fusion.doe.gov FESAC 102307-rjf 1 Topics • Budget status • ITER • NCSX • HEDLP Joint Program • Issues and Plans Note: Thank You to all who worked so hard on the three reports presented at this meeting! FESAC 102307-rjf 2 FY 2008 Fusion Energy Sciences Congressional Budget Request ($ Millions) FY 2006 FY 2007 FY 2008 Actual Sept AFP CONG Science 148.7 144.6 159.6 Facility Operations 104.2 146.3 247.5 Enabling R&D 27.8 20.8 20.8 OFES Total 280.7 311.7 427.9 DIII-D 55.1 56.7 59.7 C-Mod 21.5 22.3 23.5 NSTX 34.2 33.5 36.1 NCSX 17.8 16.6 16.6 ITER 24.6 60.0 160.0 Non-ITER 256.1 251.7 267.9 FESAC 102307-rjf 3 FY 2008 Appropriations • House Mark – The Committee recommendation for fusion energy sciences is $427,850,000, the same as the budget request, and reflecting the $100,000,000 growth in the budget for ITER. – The Committee does not support funding for a new program in High Energy Density Physics (HEDP) and provides no funds for this research area. (Resources for HEDP should be redirected to other programs). – The Committee notes that major growth in support for ITER … is affecting the overall funding picture for Fusion Energy Sciences and for the Office of Science as a whole. -
A Fusion Test Facility for Inertial Fusion
A Fusion Test Facility for Inertial Fusion The Fusion Test Facility would be part of an integrated IFE program where the essential elements are developed and implemented as systems in progressively more capable IFE oriented facilities. Fusion Test Facility (FTF) Direct laser drive Sub-megaJoule laser energy Goal of ~150 MW fusion power High flux neutron source Development path to a power plant Presented by Stephen Obenschain U.S. Naval Research Laboratory September 27 2006 Fusion Power Associates Meeting Introduction The scientific underpinnings for ICF has and is being developed via large single shot facilities. The IFE application, while greatly benefiting from this effort, requires a different and broader perspective. • Development of sufficiently efficient and durable high repetition rate drivers. • High gain target designs consistent with the energy application. • Development of economical mass production techniques for targets. • Precision target injection, tracking & laser beam steering. • Reaction chamber design and materials for a harsh environment. • Operating procedures (synchronizing a complex high duty cycle operation) • Overall economics, development time and costs. Individual IFE elements have conflicts in their optimization, and have to be developed in concert with their own purpose-built facilities. HAPL= $25M/yr High Average Power Laser program administered by NNSA See presentations by John Sethian and John Caird this afternoon. Typical GW (electrical )designs have >3 MJ laser drivers @ 5-10 Hz Target Factory Electricity -
Part 1: April 24, 2007 Presentations
UCRL-MI-231268 IFE Science and Technology Strategic Planning Workshop - Part 1: April 24, 2007 Presentations To select an individual presentation, click the table of contents entry on the next page or click the title on the agenda for Day 1 (using the Hand Tool icon). To save only a portion of this document, go to File/Print, select Adobe PDF as your printer, specify the desired range of pages, and save to a new file name. This document was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor the University of California nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or the University of California. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or the University of California, and shall not be used for advertising or product endorsement purposes. Portions of this work performed under the auspices of the U. S. Department of Energy by University of California Lawrence Livermore National Laboratory under Contract W-7405-Eng-48. Part 1 Contents Agenda ........................................................................................................................................ 3 Presentations 1. Welcome and Perspectives, Ed Synakowski, LLNL............................................................ -
Nova Laser Technology
Nova Laser Technology In building the Nova laser, we have significantly advanced many technologies, including the generation and propagation of laser beams. We have also developed innovations in the fields of alignment, diagnostics, computer control, and image processIng.• For further information contact Nova is the world's most powerful at least 10 to 30 times more energetic John F. Holzrichter (415) 423-7454. laser system. It is designed to heat and than Shiva would be needed to compress small targets, typically 0.1 cm investigate ignition conditions and in size, to conditions otherwise produced possibly to reach gains near unity. only in nuclear weapons or in the Because of the importance of such a interior of stars. Its beams can facility to the progress of inertial fusion concentrate 80 to 120 kJ of energy (in research and because of the construction 3 ns) or 80 to 120 TW of power (in time entailed (at least five to seven 100 ps) on such targets. To couple energy years), the Nova project was proposed to more favorably with the target, Nova's the Energy Research and Development laser light will be harmonically converted Administration and to Congress. It was with greater than 50% efficiency from its decided to base this system on the near-infrared fundamental wavelength proven master-oscillator, linear-amplifier (1.05-,um wavelength) to green (0.525- chain laser system used on the Argus ,um) or blue (0.35-,um) wavelengths. The and Shiva systems. We had great goals of our experiments with Nova are confidence in extending this to make accurate measurements of high neodymium-glass laser technology to the temperature and high-pressure states of 200- to 300-kJ level. -
ENGINEERING DESIGN of the NOVA LASER FACILITY for By
ENGINEERING DESIGN OF THE NOVA LASER FACILITY FOR INERTIAL-CONFINEMENT FUSION* by W. W. Simmons, R. 0. Godwin, C. A. Hurley, E. P. Wallerstein, K. Whitham, J. E. Murray, E. S. Bliss, R. G. Ozarski. M. A. Summers, F. Rienecker, D. G. Gritton, F. W. Holloway, G. J. Suski, J. R. Severyn, and the Nova Engineering Team. Abstract The design of the Nova Laser Facility for inertia! confinement fusion experiments at Lawrence Livermore National Laboratory is presented from an engineering perspective. Emphasis is placed upon design-to- performance requirements as they impact the various subsystems that comprise this complex experimental facility. - DISCLAIMER - CO;.T-CI104n--17D DEf;2 013.375 *Research performed under the auspices of the U.S. Department of Energy by the Lawrence Livermore National Laboratory under contract number W-7405-ENG-48. Foreword The Nova Laser System for Inertial Confinement Fusion studies at Lawrence Livermore National Laboratories represents a sophisticated engineering challenge to the national scientific and industrial community, embodying many disciplines - optical, mechanical, power and controls engineering for examples - employing state-of-the-art components and techniques. The papers collected here form a systematic, comprehensive presentation of the system engineering involved in the design, construction and operation of the Nova Facility, presently under construction at LLNL and scheduled for first operations in 1985. The 1st and 2nd Chapters present laser design and performance, as well as an introductory overview of the entire system; Chapters 3, 4 and 5 describe the major engineering subsystems; Chapters 6, 7, 8 and 9 document laser and target systems technology, including optical harmonic frequency conversion, its ramifications, and its impact upon other subsystems; and Chapters 10, 11, and 12 present an extensive discussion of our integrated approach to command, control and communications for the entire system. -
NRL Nike Laser Focuses on Nuclear Fusion 20 March 2013
NRL Nike Laser focuses on nuclear fusion 20 March 2013 concept, numerous laser beams are used to implode and compress a pea-sized pellet of deuterium-tritium (D-T) to extreme density and temperature, causing the atoms to fuse, resulting in the release of excess energy. In an ICF implosion, a progressively diminishing portion of the beams will engage the shrinking pellet if the focal spot diameter of the laser remains unchanged. For optimal coupling, it becomes desirable to decrease the laser focal spot size to match the reduction in the pellet's diameter, minimizing wasted energy. This is the Nike Laser -- focal zooming. Credit: U.S. "Matching the focal spot size to the pellet Naval Research Laboratory throughout the implosion process maximizes the on- target laser energy," Kehne said. "This experiment validates the engineering of focal zooming in KrF lasers to track the size of an imploding pellet in Researchers at the U.S. Naval Research inertial confinement fusion." Laboratory have successfully demonstrated pulse tailoring, producing a time varying focal spot size With single-step focal zooming implemented, the known as 'focal zooming' on the world's largest Nike laser provides independent control of pulse operating krypton fluoride (KrF) gas laser. shape, time of arrival, and focal diameter allowing greater flexibility in the profiles and pulse shapes The Nike laser is a two to three kilojoule (kJ) KrF that can be produced. The flexibility in pulse system that incorporates beam smoothing by shaping provides promising uses in both future induced spatial incoherence (ISI) to achieve one experiments and laser diagnosis.