APPENDIX a Why Magnetized Target Fusion Offers a Low-Cost
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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. -
Reactor Potential for Magnetized Target Fusion
TR.TA-A Report ISSN 1102-2051 VETENSKAP OCH ISRN KTH/ALF/--01/2--SE 1ONST KTH-ALF--01-2 KTH Reactor Potential for Magnetized Target Fusion Jon-Erik Dahlin Research and Training programme on CONTROLLED THERMONUCLEAR FUSION AND PLASMA PHYSICS (Association EURATOM/NFR) FUSION PLASMA PHYSICS ALFV N LABORATORY ROYAL INSTITUTE OF TECHNOLOGY SE-100 44 STOCKHOLM SWEDEN PLEASE BE AWARE THAT ALL OF THE MISSING PAGES IN THIS DOCUMENT WERE ORIGINALLY BLANK TRITA-ALF-2001-02 ISRN KTH/ALF/--01/2--SE Reactor Potential for Magnetized Target Fusion J.-E. Dahlin VETENSKAP OCH KONST Stockholm, June 2001 The Alfven Laboratory Division of Fusion Plasma Physics Royal Institute of Technology SE-100 44 Stockholm, Sweden (Association EURATOM/NFR) Printed by Alfven Laboratory Fusion Plasma Physics Division Royal Institute of Technology SE-100 44 Stockholm Abstract Magnetized Target Fusion (MTF) is a possible pathway to thermonuclear fusion different from both magnetic fusion and inertial confinement fusion. An imploding cylindrical metal liner compresses a preheated and magnetized plasma configuration until thermonuclear conditions are achieved. In this report the Magnetized Target Fusion concept is evaluated and a zero-dimensional computer model of the plasma, liner and circuit as a connected system is designed. The results of running this code are that thermonuclear conditions are achieved indeed, but only during a very short time. At peak compression the pressure from the compressed plasma and mag- netic field is so large reversing the liner implosion into an explosion. The time period of liner motion reversal is termed the dwell time and is crucial to the performance of the fusion system. -
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. -
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. -
Accelerating Low-Cost Plasma Heating and Assembly – ALPHA
Accelerating Low-Cost Plasma Heating and Assembly – ALPHA PROJECT DESCRIPTIONS California Institute of Technology – Pasadena, CA Prototype Tools to Establish the Viability of the Adiabatic Heating and Compression Mechanisms Required for Magnetized Target Fusion - $800,000 Caltech, in coordination with Los Alamos National Laboratory, will investigate collisions of plasma jets and targets over a wide range of parameters to characterize the scaling of adiabatic heating and compression of liner-driven magnetized target fusion plasmas. The team will propel fast magnetized plasma jets into stationary heavy gases or metal walls. The resulting collision is equivalent to a fast heavy gas or metal liner impacting a stationary magnetized target in a shifted reference frame and allows the non-destructive and rapid investigation of physical phenomena and scaling laws governing the degree of adiabaticity of liner implosions. This study will provide critical information on the interactions and limitations for a variety of possible driver and plasma target combinations being developed across the ALPHA program portfolio. Helion Energy, Inc. – Redmond, WA Staged Magnetic Compression of FRC Targets to Fusion Conditions- $3,971,264 Helion Energy, Inc. will investigate staged magnetic compression of field-reversed configuration (FRC) plasmas, building on past successes to develop a prototype that can attain higher temperatures and fuel density than previously possible. The team will use these results to assess the viability of scaling to a power reactor, which if successful would offer the benefits of simple linear geometry, attractive scaling, and compatibility with modern pulsed power electronics. Lawrence Berkeley National Laboratory – Berkeley, CA MEMS Based Ion Beam Drivers for Magnetized Target Fusion- $2,200,000 Lawrence Berkley National Laboratory (LBNL), in close collaboration with Cornell University, will develop a scalable ion beam driver based on microelectromechanical systems (MEMS) technology. -
Nuclear Fusion Power – an Overview of History, Present and Future
International Journal of Advanced Network, Monitoring and Controls Volume 04, No.04, 2019 Nuclear Fusion Power – An Overview of History, Present and Future Stewart C. Prager Department of Physics University of Wisconsin – Madison Madison, WI 53706, USA E-mail: [email protected] Summary—Fusion power offers the prospect of an allowing the nuclei to fuse together. Such conditions almost inexhaustible source of energy for future can occur when the temperature increases, causing the generations, but it also presents so far insurmountable ions to move faster and eventually reach speeds high engineering challenges. The fundamental challenge is to enough to bring the ions close enough together. The achieve a rate of heat emitted by a fusion plasma that nuclei can then fuse, causing a release of energy. exceeds the rate of energy injected into the plasma. The main hope is centered on tokamak reactors and II. FUSION TECHNOLOGY stellarators which confine deuterium-tritium plasma In the Sun, massive gravitational forces create the magnetically. right conditions for fusion, but on Earth they are much Keywords-Fusion Energy; Hydrogen Power; Nuclear Fusion harder to achieve. Fusion fuel – different isotopes of hydrogen – must be heated to extreme temperatures of I. INTRODUCTION the order of 50 million degrees Celsius, and must be Today, many countries take part in fusion research kept stable under intense pressure, hence dense enough to some extent, led by the European Union, the USA, and confined for long enough to allow the nuclei to Russia and Japan, with vigorous programs also fuse. The aim of the controlled fusion research underway in China, Brazil, Canada, and Korea. -
Compact Fusion Reactors
Compact fusion reactors Tomas Lind´en Helsinki Institute of Physics 26.03.2015 Fusion research is currently to a large extent focused on tokamak (ITER) and inertial confinement (NIF) research. In addition to these large international or national efforts there are private companies performing fusion research using much smaller devices than ITER or NIF. The attempt to achieve fusion energy production through relatively small and compact devices compared to tokamaks decreases the costs and building time of the reactors and this has allowed some private companies to enter the field, like EMC2, General Fusion, Helion Energy, Lockheed Martin and LPP Fusion. Some of these companies are trying to demonstrate net energy production within the next few years. If they are successful their next step is to attempt to commercialize their technology. In this presentation an overview of compact fusion reactor concepts is given. CERN Colloquium 26th of March 2015 Tomas Lind´en (HIP) Compact fusion reactors 26.03.2015 1 / 37 Contents Contents 1 Introduction 2 Funding of fusion research 3 Basics of fusion 4 The Polywell reactor 5 Lockheed Martin CFR 6 Dense plasma focus 7 MTF 8 Other fusion concepts or companies 9 Summary Tomas Lind´en (HIP) Compact fusion reactors 26.03.2015 2 / 37 Introduction Introduction Climate disruption ! ! Pollution ! ! ! Extinctions Ecosystem Transformation Population growth and consumption There is no silver bullet to solve these issues, but energy production is "#$%&'$($#!)*&+%&+,+!*&!! central to many of these issues. -.$&'.$&$&/!0,1.&$'23+! Economically practical fusion power 4$(%!",55*6'!"2+'%1+!$&! could contribute significantly to meet +' '7%!89 !)%&',62! the future increased energy :&(*61.'$*&!(*6!;*<$#2!-.=%6+! production demands in a sustainable way. -
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. -
Emerging Concepts Reactor Subgroup Summary J
LA-UR-99-5178 Emerging Concepts Reactor Subgroup Summary J. Hammer and R. Siemon Emerging Concepts offer unique reactor features, which may lead to a qualitative improvement in cost and maintainability, with associated increased attractiveness to the customer. Table 3 shows some of these unique features grouped by concept: Concept Motivation RFP Low external field; no disruptions Spheromak, FRC Simple geometry; small size; open axial divertor MTF, Flow Pinch Low development cost; compatible with liquid walls Levitated Dipole, Centrifugally confined High β, classical confinement; no current drive Mirrors Low physics risk; linear geometry Electrostatic, IEC, POPS Small unit size; low-cost development; high mass power density; alternate applications Fast Igniter High gain; low recirculating power Table 3: Reactor features of Emerging Concepts. Again, many examples of reactor advantages associated with Emerging Concepts could be given. As one such, there appears at first examination to be a greater accessibility for incorporating liquid walls into many such reactors. This follows from the linear, open geometry of several of the concepts, including FRC, MTF, Flow Pinch, and Mirrors. Organization The reactor subgroup, jointly with the Physics subgroup, heard presentations arranged before the conference on the 11 concepts listed below. These covered a wide range in physical parameter space with radically different reactor embodiments. The reversed field pinch and spheromak talks were held jointly with the Magnetic Confinement sessions. For each concept, a presenter introduced the concept and reviewed progress to date and important physics and reactor issues. The presenter was followed by a reviewer who brought additional insights. Concept Presenter Reviewer RFP S. -
Lll Laser Program Overview
I ~ Ellerll APR 13 1~76 ~ illid ~~WJF Destroy Telllllllllill Route - Hold mos. Prepared for U.S . Energy Research & Development lell Administration under Contract No. W-7405-Eng-48 LA.WRENCE LIVERMORE LA.BORATORY LLL LASER PROGRAM LASERS AND LASER APPLICATIONS LLL LASER PROGRAM OVERVIEW ------------------------ During the past year, substantial progress has been thermonuclear burn of microscopic targets containing made toward laser fusion, laser isotope separation, and deuterium and tritium. Experiments are being run on the development of advanced laser media, the three a single-pulse basis , the emphasis being on fa st main thrusts of the LLL laser program. diagnostics of neutron, x-ray, a-particle, and scattered Our accomplishments in laser fusion have included: laser-light fluxes from the target. Our laser source fo r • Firing and diagnosing more than 650 individual this work is the neodymium-doped-glass (Nd:glass) experiments on the O.4-TW Janus laser system laser operating in a master-oscillator, power-amplifier (including many experiments with neutron yields in configuration, where a well-characterized, mode-locked the 107 range). pulse is shaped and ampli fied by successive stages to • Producing 1 TW of on-target irradiation with a peak power of I TW in a 20-cm-diam beam. Cyclops, presently the world's most powerful Thermonuclear burn has been demonstrated. With single-beam laser. successively larger Nd :glass laser systems, we now • Completing the design for the 25-TW Shiva laser expect sequentially to demonstrate significant burn, system and ordering the long-lead-time components. light energy breakeven (equal input and output (The building to house this laser system is on schedule energies) and, finally, net energy gain.