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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. -
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. -
Experimental Results on Advanced Inertial Fusion Schemes Obtained
NUKLEONIKA 2012;57(1):3−10 ORIGINAL PAPER Experimental results Dimitri Batani, Leonida A. Gizzi, Petra Koester, Luca Labate, on advanced inertial fusion Javier Honrubia, Luca Antonelli, Alessio Morace, Luca Volpe, Jorge J. Santos, Guy Schurtz, schemes obtained Sebastien Hulin, Xavier Ribeyre, Philippe Nicolai, Benjamin Vauzour, within the HiPER project Fabien Dorchies, Wiger Nazarov, John Pasley, Maria Richetta, Kate Lancaster, Christopher Spindloe, Martin Tolley, David Neely, Michaela Kozlová, Jaroslav Nejdl, Bedrich Rus, Jerzy Wołowski, Jan Badziak Abstract. This paper presents the results of experiments conducted within the Work Package 10 (fusion experimental programme) of the HiPER project. The aim of these experiments was to study the physics relevant for advanced ignition schemes for inertial confinement fusion, i.e. the fast ignition and the shock ignition. Such schemes allow to achieve a higher fusion gain compared to the indirect drive approach adopted in the National Ignition Facility in United States, which is important for the future inertial fusion energy reactors and for realising the inertial fusion with smaller facilities. Key words: advanced ignition schemes • fast ignition • shock ignition • inertial fusion • propagation of fast electrons • short-pulse ultra-high-intensity laser • shock compressed matter • cylindrical implosions Introduction D. Batani , J. J. Santos, G. Schurtz, S. Hulin, In 2006 the European Strategy Forum on Research X. Ribeyre, P. Nicolai, B. Vauzour, F. Dorchies Infrastructures (ESFRI) included the HiPER Project CELIA, Université de Bordeaux/CNRS/CEA, (European High Power Laser Energy Research Facility) Talence, 33405, France, in the European roadmap for Research Infrastructures. Tel.: +33 0 5 4000 3753, Fax: + 33 0 5 4000 2580, The goals of the HiPER project are to perform a feasi- E-mail: [email protected] bility study, choose a design and then construct a high- -energy laser facility for research on the production of L. -
Visualizing Fast Electron Energy Transport Into Laser-Compressed High-Density Fast-Ignition Targets
ARTICLES PUBLISHED ONLINE: 11 JANUARY 2016 | DOI: 10.1038/NPHYS3614 Visualizing fast electron energy transport into laser-compressed high-density fast-ignition targets L. C. Jarrott1†, M. S. Wei2*, C. McGuey1, A. A. Solodov3,4, W. Theobald3, B. Qiao1, C. Stoeckl3, R. Betti3,4, H. Chen5, J. Delettrez3, T. Döppner5, E. M. Giraldez2, V. Y. Glebov3, H. Habara6, T. Iwawaki6, M. H. Key5, R. W. Luo2, F. J. Marshall3, H. S. McLean5, C. Mileham3, P. K. Patel5, J. J. Santos7, H. Sawada8, R. B. Stephens2, T. Yabuuchi6 and F. N. Beg1* Recent progress in kilojoule-scale high-intensity lasers has opened up new areas of research in radiography, laboratory astrophysics, high-energy-density physics, and fast-ignition (FI) laser fusion. FI requires ecient heating of pre-compressed high-density fuel by an intense relativistic electron beam produced from laser–matter interaction. Understanding the details of electron beam generation and transport is crucial for FI. Here we report on the first visualization of fast electron spatial energy deposition in a laser-compressed cone-in-shell FI target, facilitated by doping the shell with copper and imaging the K-shell radiation. Multi-scale simulations accompanying the experiments clearly show the location of fast electrons and reveal key parameters aecting energy coupling. The approach provides a more direct way to infer energy coupling and guide experimental designs that significantly improve the laser-to-core coupling to 7%. Our findings lay the groundwork for further improving eciency, with 15% energy coupling predicted in FI experiments using an existing megajoule-scale laser driver. usion ignition and burn may be achieved through inertial its energy into the compressed core. -
FCI in France Status and Perspective
FCI in France status and perspective Thierry Massard Chief scientist CEA Defense and Security Guy Schurtz (CELIA), Benoit Canaud (CEA), Laurent Grémillet (CEA),Christine Labaune(CNRS) Fusion Power Associates – Washington DC – 1-2 December 2010 Outline • ICF in France : a long history of successes • ICF for energy : a place in the French energy vision ? • LMJ / PETAL a key facility for the IFE in Europe • How France scientific community participates in HiPER (European program for IFE faisability demoinstration) • The French strategy • A world wide forum is necessary for IFE ICF reserach in France was initiated at Ecole Polytechnique, In 1964 with the support of CEA-Limeil In 40 years, 5 national generations of lasers were commissioned, Rubis laser : CO2 laser : Nd laser : 2 beams-200 J – 600 ps (w, 2w, 4w) (1980) Nd laser : 6 beams – 600 J -600 ps (w, 2w, 4w) (1985-2002) Ti/Sa : 100 TW LULI2000 : 2 beams – 2 kJ – 1.5 ns (w, 2w, 3w) 1,00E+15 In 1968 the first fusion events are observed 1,00E+14 100TW Pico2000 1,00E+13 P(W) 1,00E+12 Nd-6F LULI2000 1,00E+11 Nd-1F 1,00E+10 1,00E+09 CO 2 1,00E+08 Rubis 1960 1970 1980 1990 2000 2010 Year C6 laser, delivering up to 600 J Today several critical laser facilities and labs in France • Ecole Polytechnique {LOA, LULI}, • CELIA (Bordeaux) • CEA (Bruyeres, Saclay and Bordeaux) • LCD/ENSMA fs ps ns 6 10 PW LMJ 10 5 LIL 4 10 PW / LIL Nano 2000 1000 ELI TW Pico 2000 Lucia : objectif : 100 J – 10 Hz 100 LULI 100TW Alise 10 LOA LIXAM (Alise) Energie [J] 1 LOA CEA/DSM GW 0,1 CELIA 0,01 0,01 0,1 1 10 100 1000 -
Bright Γ Rays Source and Nonlinear Breit-Wheeler Pairs in the Collision of High Density Particle Beams
PHYSICAL REVIEW ACCELERATORS AND BEAMS 22, 023402 (2019) Bright γ rays source and nonlinear Breit-Wheeler pairs in the collision of high density particle beams † ‡ F. Del Gaudio,1,* T. Grismayer,1, R. A. Fonseca,1,2 W. B. Mori,3 and L. O. Silva1, 1GoLP/Instituto de Plasmas e Fusão Nuclear, Instituto Superior T´ecnico, Universidade de Lisboa, 1049-001 Lisbon, Portugal 2DCTI/ISCTE Instituto Universitário de Lisboa, 1649-026 Lisboa, Portugal 3Departments of Physics & Astronomy and of Electrical Engineering, University of California Los Angeles, Los Angeles, California 90095, USA (Received 13 April 2018; published 8 February 2019) The collision of ultrashort high-density e− or e− and eþ beams at 10s of GeV, to be available at the FACET II and in laser wakefield accelerator experiments, can produce highly collimated γ rays (few GeVs) with peak brilliance of 1027 ph=smm2 mrad20.1%BW and up to 105 nonlinear Breit-Wheeler pairs. We provide analytical estimates of the photon source properties and of the yield of secondary pairs, finding excellent agreement with full-scale 3D self-consistent particle-in-cell simulations that include quantum electrodynamics effects. Our results show that beam-beam collisions can be exploited as secondary sources of γ rays and provide an alternative to beam-laser setups to probe quantum electrodynamics effects at the Schwinger limit. DOI: 10.1103/PhysRevAccelBeams.22.023402 I. INTRODUCTION speed of light, e is the elementary charge and ℏ is the Planck constant. The classical regime is identified by χ ≪ 1, the full Colliders are a cornerstone of fundamental physics of quantum regime by χ ≫ 1 and the quantum transition paramount importance to probe the constituents of matter. -
Sauter–Schwinger Effect with a Quantum Gas
PAPER • OPEN ACCESS Sauter–Schwinger effect with a quantum gas To cite this article: A M Piñeiro et al 2019 New J. Phys. 21 083035 View the article online for updates and enhancements. This content was downloaded from IP address 129.2.180.214 on 21/08/2019 at 18:49 New J. Phys. 21 (2019) 083035 https://doi.org/10.1088/1367-2630/ab3840 PAPER Sauter–Schwinger effect with a quantum gas OPEN ACCESS A M Piñeiro , D Genkina, Mingwu Lu and I B Spielman RECEIVED Joint Quantum Institute, National Institute of Standards and Technology and University of Maryland, Gaithersburg, MD 20899, United 26 March 2019 States of America REVISED 18 July 2019 E-mail: [email protected] and [email protected] ACCEPTED FOR PUBLICATION Keywords: quantum gases, Sauter–Schwinger effect, particle creation, quantum simulation 2 August 2019 PUBLISHED 21 August 2019 Abstract Original content from this The creation of particle–antiparticle pairs from vacuum by a large electric field is at the core of work may be used under the terms of the Creative quantum electrodynamics. Despite the wide acceptance that this phenomenon occurs naturally when − Commons Attribution 3.0 18 1 electric field strengths exceed Ec≈10 Vm , it has yet to be experimentally observed due to the licence. fi Any further distribution of limitations imposed by producing electric elds at this scale. The high degree of experimental control this work must maintain present in ultracold atomic systems allow experimentalists to create laboratory analogs to high-field attribution to the author(s) and the title of phenomena. -
Nonperturbative QED Vacuum Birefringence
Prepared for submission to JHEP Nonperturbative QED vacuum birefringence V.I.Denisov E.E.Dolgaya and V.A.Sokolov Physics Department, Moscow State University, Moscow, 119991, Russia E-mail: [email protected], [email protected], [email protected] Abstract: In this paper we represent nonperturbative calculation for one-loop Quantum Electrodynamics (QED) vacuum birefringence in presence of strong magnetic field. The dispersion relations for electromagnetic wave propagating in strong magnetic field point to retention of vacuum birefringence even in case when the field strength greatly exceeds Sauter-Schwinger limit. This gives a possibility to extend some predictions of perturbative QED such as electromagnetic waves delay in pulsars neighbourhood or wave polarization state changing (tested in PVLAS) to arbitrary magnetic field values. Such expansion is especially important in astrophysics because magnetic fields of some pulsars and magnetars greatly exceed quantum magnetic field limit, so the estimates of perturbative QED effects in this case require clarification. Keywords: QED vacuum birefringence, Electromagnetic processes in strong field, Non- perturbative effects arXiv:1612.09086v2 [hep-ph] 30 Dec 2016 Contents 1 Introduction 1 2 Constitutive relations for nonperturbative QED 2 3 Electromagnetic wave propagation in strong magnetic field 4 4 QED vacuum birefringence extension on nonperturbative regime 6 5 Conclusion 9 1 Introduction From the very beginning, radiative corrections to the QED Lagrangian coming from the vacuum fluctuations have been the subject of a great interest. Such corrections, accounted on background of constant and homogeneous electromagnetic field, lead to Heisenberg- Euler effective Lagrangian [1]. The scale parameter for nonlinearities in Heisenberg-Euler electrodynamics (characteristic quantum electrodynamic induction or Schwinger limit for electric field) B = E = m2c3/e~ = 4.41 1013G distinguishes different regimes of the c c · theory. -
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. -
ITER - Wikipedia 1 of 23
ITER - Wikipedia 1 of 23 Coordinates: 43.70831°N 5.77741°E ITER ITER (originally the International ITER Thermonuclear Experimental Reactor[1]) is an international nuclear fusion research and engineering megaproject, which will be the world's largest magnetic confinement plasma physics experiment. It is an experimental tokamak nuclear fusion reactor that is being built next to the Cadarache facility in Saint-Paul-lès-Durance, in Provence, southern France.[2] The ITER thermonuclear fusion reactor has been designed to produce a fusion plasma equivalent to 500 megawatts (MW) of thermal output power for around twenty minutes while 50 megawatts of Thirty-five participating nations thermal power are injected into the tokamak, Formation 24 October 2007 resulting in a ten-fold gain of plasma heating power.[3] Thereby the machine aims to demonstrate Headquarters Saint-Paul-lès- the principle of producing more thermal power from Durance, France the fusion process than is used to heat the plasma, Director- Bernard Bigot something that has not yet been achieved in any General fusion reactor. The total electricity consumed by the Website www.iter.org (https:// reactor and facilities will range from 110 MW up to www.iter.org/) 620 MW peak for 30-second periods during plasma operation.[4] Thermal-to-electric conversion is not ITER included in the design because ITER will not produce sufficient power for net electrical production. The emitted heat from the fusion reaction will be vented to the atmosphere.[5][6] The project is funded and run by seven member entities—the European Union, India, Japan, China, Russia, South Korea and the United States.