Nova Laser Technology
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Laboratory Astrophysics with Lasers Chantal Stehlé
Laboratory Astrophysics with lasers Chantal Stehlé LERMA (Laboratoire d’Etudes de la Ma4ère et du Rayonnement en Astrophysique et Atmosphères) This work is partly supported by French state funds managed by the ANR within the InvesBssements d'Avenir programme under reference ANR-11-IDEX-0004-02. Plasma astrophysics see for instance Savin et al. « Lab astro white paper », 2010 Perimeter Methods • Microscopic physical • Experiments processes (opacity, EOS) • Theory, databases • • MulBscale, mulphysics Numerical simulaons • Links to observaons processes (e.g. magne4c reconnecon, shock waves, instabili4es …) Tools • Study of large scale scaled • Medium size lab. processes, (e.g. stellar jets) experiments • Large scale faciliBes (lasers and pinches ) • Super-compung ressources OUTLINE • IntroducBon • Stellar Opacity • EOS for gazeous planets • Scaling • Accreon & Ejecon processes in Young Stars • Conclusion Opacity for stellar interiors From Turck Chièze et al. ApSS 2010 4 Opacity An example of opacity : For a optically thick medium, Hydrogen( Stehlé et al 1993) • LTE is ~ valid -> near blackbody radiaon κν/ρ • The monochromac radiave flux Fν ! is proporBonal to the gradient of rad. Energy and to 1/κν (The radia4on tends to escape from regions where κν is low, ie between lines) hν • The frequency averaged flux <F> is linked to the Rosseland opacity κR. 1 3 dν dB (T) / dT 16 σ T dT 1 ∫ κ ν < F > = and = ν d dB (T) / dT 3 κ R dz κ R ∫ ν ν 5 CEPHEIDS: the enigma Strong periodic (P~ 1 – 50 days) Rela4on P-L : variaons of luminosity L, Teff, and distance calibrator radius. Enveloppe 2 The pulsaon (κ mechanism) log(κR in g/cm ) 2 • in the external part of the stellar envelope 1.5 • linked to an increase of the opacity 1 4 6 -7 -2 3 0.5 10 < T < 10 K (10 < ρ < 10 g/cm ) 0 Hence radiaon is blocked in the internal layers, -> heang -> expansion and beang Core 34 32 30 28 log(External Mass in g ) 2 In the 90’, no code was able Temperature in K, κ in cm /g for M* = 5 M8, Y=0.25, Z=0.08, to reproduce the pulsa6on. -
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. -
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. -
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. -
Lasers Join the Quest for Fusion Energy
1974 Lasers and ICF Lasers Join the Quest to gain a better understanding of laser plasma physics and thermonuclear physics and to demonstrate for Fusion Energy laser-induced compression and thermonuclear burn of deuterium–tritium. It was also used to improve the LASNEX computer code developed for laser With the goal of achieving energy gain fusion predictions. Janus was just the In 1975, the one-beam Cyclops laser through inertial confinement fusion beginning of the development, in quick began operation, performing important (ICF) as its mission, the Laser Program succession, of a series of lasers, each target experiments and testing optical constructed its first laser for ICF building on the knowledge gained from designs for future lasers. The next year, experiments in 1974. Named Janus, the last, leading to the National Ignition the two-beam Argus was built. Use of the two-beam laser was built with about Facility (NIF), currently performing Argus increased knowledge about laser– 100 pounds of laser glass. experiments. The pace of laser target interactions and laser propagation The first Livermore laser for construction matched the growth limits, and it helped the ICF program prepared the Laboratory to take the With the 20-beam ICF research, Janus, had Under the leadership of John Emmett, in ICF diagnostics capabilities, develop technologies needed for the next major step, construction of the Shiva laser in 1977, the two beams and produced who headed the Laser Program from computer simulation tools, and next generation of laser fusion systems. 192-beam NIF (see Year 1997), where Laboratory established 10 joules of energy. -
The Effect of Surface Processing Methods on the Laser Induced Damage Threshold of Fused Silica
The Effect of Surface Processing Methods on the Laser Induced Damage Threshold of Fused Silica by Weiran Duan A thesis submitted in partial fulfilment for the requirements for the degree of PhD at the University of Central Lancashire October 2014 2 To my family i Declaration I declare that while registered as a candidate for the research degree, I have not been a registered candidate or enrolled student for another award of the University or other academic or professional institution. I declare that no material contained in the thesis has been used in any other submission for an academic award and is solely my own work. Weiran Duan ii Abstract High peak power laser systems, such as National Ignition Facility (NIF), Laser Mega Joule (LMJ), and High Power laser Energy Research facility (HiPER), include a large amount of optics. Fused silica glass is one of the most common optical materials which is used in these high peak power laser systems owing to its excellent optical properties, especially for the 355nm ultraviolet laser. However, it is generally found that fused silica optics damage under irradiation with a high peak power laser beam, and the laser induced damage (LID) becomes the limit to increasing the laser power. Theoretically, the laser induced damage threshold (LIDT) of fused silica substrates is high, while it drops significantly due to the poor surface quality created in the manufacturing process. This project aims to find a series of fused silica optical surface processing techniques which are able to improve the surface quality and increase its LIDT when irradiated using high peak power lasers. -
Nd Lu Caf2 for High-Energy Lasers Simone Normani
Nd Lu CaF2 for high-energy lasers Simone Normani To cite this version: Simone Normani. Nd Lu CaF2 for high-energy lasers. Physics [physics]. Normandie Université, 2017. English. NNT : 2017NORMC230. tel-01689866 HAL Id: tel-01689866 https://tel.archives-ouvertes.fr/tel-01689866 Submitted on 22 Jan 2018 HAL is a multi-disciplinary open access L’archive ouverte pluridisciplinaire HAL, est archive for the deposit and dissemination of sci- destinée au dépôt et à la diffusion de documents entific research documents, whether they are pub- scientifiques de niveau recherche, publiés ou non, lished or not. The documents may come from émanant des établissements d’enseignement et de teaching and research institutions in France or recherche français ou étrangers, des laboratoires abroad, or from public or private research centers. publics ou privés. THESE Pour obtenir le diplôme de doctorat Physique Préparée au sein de l’Université de Caen Normandie Nd:Lu:CaF2 for High-Energy Lasers Étude de Cristaux de CaF2:Nd:Lu pour Lasers de Haute Énergie Présentée et soutenue par Simone NORMANI Thèse soutenue publiquement le 19 octobre 2017 devant le jury composé de M. Patrice CAMY Professeur, Université de Caen Normandie Directeur de thèse M. Alain BRAUD MCF HDR, Université de Caen Normandie Codirecteur de thèse M. Jean-Luc ADAM Directeur de Recherche, CNRS Rapporteur Mme. Patricia SEGONDS Professeur, Université de Grenoble Rapporteur M. Jean-Paul GOOSSENS Ingénieur, CEA Examinateur M. Maurizio FERRARI Directeur de Recherche, CNR-IFN Examinateur Thèse dirigée par Patrice CAMY et Alain BRAUD, laboratoire CIMAP Université de Caen Normandie Nd:Lu:CaF2 for High-Energy Lasers Thesis for the Ph.D. -
X-Ray Lasing: the Novette Laser
X-Ray Lasing: The Novelle Laser Although the Novette laser system served primarily as a test bed for advanced concepts of targets and lasers for the Nova system, its flexibility enabled us to use it for research that led to the world's first demonstration of x-ray lasing. ver the past decade, we have harmonic conversion for producing For further information contact built a series of ever more light of higher frequencies (that is, Kenneth R. Manes (415) 423-6207. O powerful and complex laser shorter wavelengths). With Novette, systems Ganus, Argus, Shiva, and now we demonstrated a system for Nova) devoted to research on inertial routinely generating powerful beams confinement fusion (ICF) and weapon of green (0.53-pm) and ultraviolet physics. However, the Novette laser (0.35- and 0.26-pm) light, greatly Fig. 1 system (Fig. 1) did not fit neatly into broadening the range of feasible Artist's rendering of the business end of this series. Although it shared physics experiments. We confirmed the Novette laser system, showing the target characteristics of the other lasers, such that laser-plasma coupling, and chamber, the harmonic-conversion arrays, and the extensive diagnostic instrumentation. as master-oscillator power-amplifier therefore the performance of the rCF The laser amplifier chains are out of the (MOPA) architecture, neodymium capsules, is greatly enhanced if green picture, folded trombone style to fit into the glass amplifiers, and a 1.053-pm or ultraviolet light is used instead of available space. fundamental wavelength, in many ways Novette was considerably less complex than its predecessor, the Shiva laser. -
Radiation Safety Plan
RADIATION SAFETY PLAN ENVIRONMENTAL NOVA SOUTHEASTERN HEALTH AND SAFETY UNIVERSITY POLICY/PROCEDURE POLICY/PROCEDURE TITLE: Radiation Safety Plan NUMBER: 9 DOCUMENT HISTORY OWNER: Facilities Management/AHIS Date: 1 Sept 2011 APPROVED: NSU Radiation Safety Committee Date: 1 Sept 2011 IMPLEMENTED: Date: 1 Oct 2010 RETIRED: Date: Date: Revision No. Review / Changes Reviewer 1/2017 1 Remove Gamma Irradiator reference RSO-5 form RSC 1/2017 2 Change EHS Committee to Radiation Safety RSC Committee (RSC) 1/2017 3 Change references from EHS to RSO RSC 4/2019 4 Edit section 5.4 to remove shipping building RSO RADIATION SAFETY PLAN RADIATION SAFETY PLAN Table of Contents Section 1: Introduction ........................................................................................................ 4 Section 2: Biological Effects and Exposure Protection ......................................................... 9 Section 3: Responsibilities ................................................................................................. 12 Section 4: License Requirements ....................................................................................... 15 Section 5: Authorization and Procurement of Radioactive Materials ................................ 16 Section 6: Training ............................................................................................................. 19 Section 7: Personnel Monitoring and Occupational Dose Limits ....................................... 22 Section 8: Signs and Labels ............................................................................................... -
2Fi Lawrence Livermore Laboratory I*^P^*S
V PREPRINT UCRL- 77944 Ur,\>\--m'>te^-2fi Lawrence Livermore Laboratory STATUS OF LARGE NEODYHIUM GLASS LASERS James A. Glaze, William W. Simmons and Wilhelm F. Hagen March ID, 1976 mm This Paper was Prepared for Submission to the Society of Photo-Optical Instrumentation Engineers SPIE Meeting, Reston, VA March 22-23, 1976 This is a preprint ot a paper intended for publication in a journal or proceedings. Since changes may be made before publication, this preprint is made available with the understanding that it will not be cited or reproduced without the permission of the author. i*^P^*S' ««*- -»v«>*^_ DiSTRiKUTiONC; 7602 STATUS OF LARGE NEODYMIUM GLASS LASERS* •ponum] by llw Van* Stu „ o| M[l Blmc*i ng PttritrmtM A« Canes A. Glaje, William H. Simmons and Wlhelm F. Hagen uitKnnmtion. 01 IIKU tiqitiqRt, Laser Fusion Division, Lawrence Livermore Laboratory nmnir. <ieir» 01 tngfttd Llvermore, California 94550 *IR£t» ottTIfcnitttllly f.tth mrnw en>,«l* owned (HJHi. Introduction The Nd:Glass laser is used extensively throughout the world for laser fusion and laser plasma Inter action studies. Its popularity, to a large extent, stems from the fact that 1t 1s capable of operating reliably in the subnanosecond-terawatt power regime. In addition, the technology necessary to combine a large number of laser chains to produce a system capable of multi-terawatt performance currently exists and is being applied. At the Lawrence Livermore Laboratory two large laser systems are currently in operation and two are under construction. The OANUS and CYCLOPS systems produce 0.5 and 1 terawatt of focusable power 1n 0.1 ns respectively. -
Signature Redacted %
EXAMINATION OF THE UNITED STATES DOMESTIC FUSION PROGRAM ARCHW.$ By MASS ACHUSETTS INSTITUTE Lauren A. Merriman I OF IECHNOLOLGY MAY U6 2015 SUBMITTED TO THE DEPARTMENT OF NUCLEAR SCIENCE AND ENGINEERING I LIBR ARIES IN PARTIAL FULFILLMENT OF THE REQUIREMENTS FOR THE DEGREE OF BACHELOR OF SCIENCE IN NUCLEAR SCIENCE AND ENGINEERING AT THE MASSACHUSETTS INSTITUTE OF TECHNOLOGY FEBRUARY 2015 Lauren A. Merriman. All Rights Reserved. - The author hereby grants to MIT permission to reproduce and to distribute publicly Paper and electronic copies of this thesis document in whole or in part. Signature of Author:_ Signature redacted %. Lauren A. Merriman Department of Nuclear Science and Engineering May 22, 2014 Signature redacted Certified by:. Dennis Whyte Professor of Nuclear Science and Engineering I'l f 'A Thesis Supervisor Signature redacted Accepted by: Richard K. Lester Professor and Head of the Department of Nuclear Science and Engineering 1 EXAMINATION OF THE UNITED STATES DOMESTIC FUSION PROGRAM By Lauren A. Merriman Submitted to the Department of Nuclear Science and Engineering on May 22, 2014 In Partial Fulfillment of the Requirements for the Degree of Bachelor of Science in Nuclear Science and Engineering ABSTRACT Fusion has been "forty years away", that is, forty years to implementation, ever since the idea of harnessing energy from a fusion reactor was conceived in the 1950s. In reality, however, it has yet to become a viable energy source. Fusion's promise and failure are both investigated by reviewing the history of the United States domestic fusion program and comparing technological forecasting by fusion scientists, fusion program budget plans, and fusion program budget history. -
Nuclear Diagnostics for Inertial Confinement Fusion (ICF) Plasmas
PSFC/JA-20-4 Nuclear diagnostics for Inertial Confinement Fusion (ICF) plasmas J. A. Frenje January 2020 Plasma Science and Fusion Center Massachusetts Institute of Technology Cambridge MA 02139 USA The work described herein was supported in part by US DOE (Grant No. DE-FG03-03SF22691), LLE (subcontract Grant No. 412160-001G) and the Center for Advanced Nuclear Diagnostics (Grant No. DE-NA0003868). Reproduction, translation, publication, use and disposal, in whole or in part, by or for the United States government is permitted. Submitted to Plasma Physics and Controlled Fusion Nuclear Diagnostics for Inertial Confinement Fusion (ICF) Plasmas J.A. Frenje1 1Massachusetts Institute of Technology, Cambridge, MA 02139, USA Email: [email protected] The field of nuclear diagnostics for Inertial Confinement Fusion (ICF) is broadly reviewed from its beginning in the seventies to present day. During this time, the sophistication of the ICF facilities and the suite of nuclear diagnostics have substantially evolved, generally a consequence of the efforts and experience gained on previous facilities. As the fusion yields have increased several orders of magnitude during these years, the quality of the nuclear-fusion-product measurements has improved significantly, facilitating an increased level of understanding about the physics governing the nuclear phase of an ICF implosion. The field of ICF has now entered an era where the fusion yields are high enough for nuclear measurements to provide spatial, temporal and spectral information, which have proven indispensable to understanding the performance of an ICF implosion. At the same time, the requirements on the nuclear diagnostics have also become more stringent.