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Superconducting Magnets Research for a Viable US Fusion Program Joseph V
Superconducting Magnets Research for a Viable US Fusion Program Joseph V. Minervini1, Leslie Bromberg1, Peter J. Lee2, David C. Larbalestier2, Introduction Magnet systems are the ultimate enabling technology for magnetic confinement fusion devices. Powerful magnetic fields are required for confinement of the plasma, and, depending on the magnetic configuration, dc and/or pulsed magnetic fields are required for plasma initiation, ohmic heating, inductive current drive, plasma shaping, equilibrium and stability control. Almost all design concepts for power producing commercial fusion reactors rely on superconducting magnets for efficient and reliable production of these magnetic fields. Future superconducting magnets for fusion applications require improvements in materials, components, and configurations to significantly enhance the feasibility and practicality of fusion reactors as an energy source. A demonstration of large-scale demountable High Temperature Superconducting (HTS) magnets could revolutionize fusion energy development, dramatically reducing program cost and development time. Background OFES established and maintained a robust magnet technology development for several decades. Until the end of the ITER EDA (1998), the magnet technology R&D program was arguably the most successful of all enabling magnet technology programs. Most of the laboratories and universities performing superconducting magnet R&D had robust programs. A major milestone was the first (and only) successful operation of the massive superconducting magnet system for MFTF-B at LLNL in 1986. The high point was the successful completion (1999) and operation (2000) of the ITER CS Model Coil (CSMC). Since that time, funding for the development of superconducting magnets and almost all other enabling technologies has been on a steady decline, leading to the proposed magnet technology budget for FY 2013 of $765,000 or 0.19% of the total fusion budget. -
ERC Implementing Arrangements Call for Expression of Interest 2017
ERC Implementing Arrangements Call for Expression of Interest 2017 Project ID: Project Acronym: Evaluation Panel: 681178 G-EDIT LS1 Principal Investigator: Dr Mariusz Nowacki Host Institution: Universitat Bern - CH Mechanisms of RNA-guided genome editing in eukaryotes The goal of this project is to contribute to our understanding of RNA-mediated epigenetic mechanisms of genome regulation in eukaryotes. Ciliated protozoa offer a fantastic opportunity to investigate the complex process of trans-generational programming of chromosomal rearrangements, which is thought to serve as a form of immune defense against invasive DNA. Developmental processes in ciliates include extensive rearrangements of the germline DNA, including elimination of transposons and the precise excision of numerous single-copy elements derived from transposons. This process is considered to be maternally controlled because the maternal genome provides essential information in the form of RNA that determines the offspring's genome content and organization. This programmed DNA subtraction, the so-called ‘RNA scanning’ process, is mediated by trans-generational comparison between the germline and the maternal somatic genome. One of the most intriguing questions is how a complex population of small RNAs representing the entire germline genome can be compared to the entire rearranged maternal genome, resulting in the efficient selection of germline-specific RNAs, which are able to target DNA deletions in the developing genome. All this occurs in a very short time and involves a massively coordinated transport of all the components between three types of nuclei. This project focuses on characterizing the molecular machinery that can orchestrate the massive genome rearrangements in ciliates through nucleic acids and protein interactions. -
Nuclear Fusion
Copyright © 2016 by Gerald Black. Published by The Mars Society with permission NUCLEAR FUSION: THE SOLUTION TO THE ENERGY PROBLEM AND TO ADVANCED SPACE PROPULSION Gerald Black Aerospace Engineer (retired, 40+ year career); email: [email protected] Currently Chair of the Ohio Chapter of the Mars Society Presented at Mars Society Annual Convention, Washington DC, September 22, 2016 ABSTRACT Nuclear fusion has long been viewed as a potential solution to the world’s energy needs. However, the government sponsored megaprojects have been floundering. The two multi-billion- dollar flagship programs, the International Tokamak Experimental Reactor (ITER) and the National Ignition Facility (NIF), have both experienced years of delays and a several-fold increase in costs. The ITER tokamak design is so large and complex that, even if this approach succeeds, there is doubt that it would be economical. After years of testing at full power, the NIF facility is still far short of achieving its goal of fusion ignition. But hope is not lost. Several private companies have come up with smaller and simpler approaches that show promise. This talk highlights the progress made by one such private company, namely LPPFusion (formerly called Lawrenceville Plasma Physics). LPPFusion is developing focus fusion technology based on the dense plasma focus device and hydrogen-boron 11 fuel. This approach, if it works, would produce a fusion power generator small enough to fit in a truck. This device would produce no radioactivity, there would be no possibility of a meltdown or other safety issues, and it would be more economical than any other source of electricity. -
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. -
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. -
Fusion Energy Science Opportunities in Emerging Concepts
Fusion Energy Science Opportunities in Emerging Concepts Los Alamos National Laboratory Report -- LA-UR-99-5052 D. C. Barnes Los Alamos National Laboratory For the Emerging Concepts Working Group Convenors: J. Hammer Lawrence Livermore National Laboratory A. Hassam University of Maryland D. Hill Lawrence Livermore National Laboratory A. Hoffman University of Washington B. Hooper Lawrence Livermore National Laboratory J. Kesner Massachusetts Institute of Technology G. Miley University of Illinois J. Perkins Lawrence Livermore National Laboratory D. Ryutov Lawrence Livermore National Laboratory J. Sarff University of Wisconsin R. E. Siemon Los Alamos National Laboratory J. Slough University of Washington M. Yamada Princeton Plasma Physics Laboratory I. Introduction The development of fusion energy represents one of the few long-term (multi-century time scale) options for providing the energy needs of modern (or postmodern) society. Progress to date, in parameters measuring the quality of confinement, for example, has been nothing short of stellar. While significant uncertainties in both physics and (particularly) technology remain, it is widely believed that a fusion reactor based on the tokamak could be developed within one or two decades. It is also widely held that such a reactor could not compete economically in the projected energy market. A more accurate statement of projected economic viability is that the uncertainty in achieving commercial success is sufficient that the large development costs required for such a program are not justified at this time. While technical progress has been spectacular, schedule estimates for achieving particular milestones along the path of fusion research and development have proven notoriously inaccurate. This inaccuracy reflects two facts. -
Retarding Field Analyzer (RFA) for Use on EAST
Magnetic Confinement Fusion C. Xiao and STOR-M team Plasma Physics Laboratory University of Saskatchewan Saskatoon, Canada \ Outline Magnetic Confinement scheme Progress in the world Tokamak Research at the University of Saskatchewan 2 CNS-2019 Fusion Session, June 24, 2019 Magnetic Confinement Scheme 3 CNS-2019 Fusion Session, June 24, 2019 Charged particle motion in straight magnetic field A charged particle circulates around the magnetic field lines (e.g., produced in a solenoid) Cross-field motion is restricted within Larmor radius 푚푣 푟 = 퐿 푞퐵 Motion along the field lines is still free End loss to the chamber wall Chamber Wall 4 CNS-2019 Fusion Session, June 24, 2019 Toriodal geometry is the solution However, plasma in simple toroidal field drifts to outboard on the wall 5 CNS-2019 Fusion Session, June 24, 2019 Tokamak Bend solenoid to form closed magnetic field lines circular field line without ends no end-loss. Transformer action produces a huge current in the chamber Generate poloidal field Heats the plasma Tokamak: abbreviation of Russian words for toroidal magnetic chamber 6 CNS-2019 Fusion Session, June 24, 2019 Stellarator • The magnetic field are generated by complicated external coils • No plasma current, no disruptions • Engineering is challenge 7 CNS-2019 Fusion Session, June 24, 2019 Wendelstein 7-X, Greifswald, Germany • Completed in October 2015 • Superconducting coils • High density and high temperature have been achieved 8 CNS-2019 Fusion Session, June 24, 2019 Reversed Field Pinch • Toroidal field reverses direction at the edge • The magnetic field are generated by current in plasma • Toroidal filed and poloidal field are of similar strength. -
NIAC 2011 Phase I Tarditti Aneutronic Fusion Spacecraft Architecture Final Report
NASA-NIAC 2001 PHASE I RESEARCH GRANT on “Aneutronic Fusion Spacecraft Architecture” Final Research Activity Report (SEPTEMBER 2012) P.I.: Alfonso G. Tarditi1 Collaborators: John H. Scott2, George H. Miley3 1Dept. of Physics, University of Houston – Clear Lake, Houston, TX 2NASA Johnson Space Center, Houston, TX 3University of Illinois-Urbana-Champaign, Urbana, IL Executive Summary - Motivation This study was developed because the recognized need of defining of a new spacecraft architecture suitable for aneutronic fusion and featuring game-changing space travel capabilities. The core of this architecture is the definition of a new kind of fusion-based space propulsion system. This research is not about exploring a new fusion energy concept, it actually assumes the availability of an aneutronic fusion energy reactor. The focus is on providing the best (most efficient) utilization of fusion energy for propulsion purposes. The rationale is that without a proper architecture design even the utilization of a fusion reactor as a prime energy source for spacecraft propulsion is not going to provide the required performances for achieving a substantial change of current space travel capabilities. - Highlights of Research Results This NIAC Phase I study provided led to several findings that provide the foundation for further research leading to a higher TRL: first a quantitative analysis of the intrinsic limitations of a propulsion system that utilizes aneutronic fusion products directly as the exhaust jet for achieving propulsion was carried on. Then, as a natural continuation, a new beam conditioning process for the fusion products was devised to produce an exhaust jet with the required characteristics (both thrust and specific impulse) for the optimal propulsion performances (in essence, an energy-to-thrust direct conversion). -
Plasma Physics Division Fachverband Plasmaphysik (P)
Hannover 2016 – P Overview Plasma Physics Division Fachverband Plasmaphysik (P) Navid Mahdizadeh ABB Switzerland Ltd Brown-Boveri-Strasse 5 CH-8050 Zürich [email protected] Overview of Invited Talks and Sessions (Lecture rooms b302 and b305; Poster Empore Lichthof) Invited Talks P 2.1 Mon 11:00–11:30 b305 Mid-infrared cavity enhanced absorption spectroscopy of gas and surface species — ∙Jean-Pierre van Helden, Norbert Lang, Andy Nave, Jürgen Röpcke P 3.1 Mon 14:30–15:00 b302 Advances in Laser Manipulation of Dusty Plasmas — ∙Jan Schablinski, Frank Wieben, Dietmar Block P 4.1 Mon 14:30–15:00 b305 Impact of electron attachment processes on nonthermal plasmas — ∙Jürgen Meichsner, Sebastian Nemschokmichal, Robert Tschiersch, Thomas Wegner P 6.1 Tue 11:00–11:30 b302 ns-Pulsed Micro-Plasmas at Atmospheric Pressures — ∙Uwe Czarnetzki P 7.1 Tue 11:00–11:30 b305 Erste Ergebnisse an Wendelstein 7-X — ∙Hans-Stephan Bosch, W7-X Team P 8.1 Tue 14:30–15:00 b302 Nanometer-scale characterization of laser-driven plasmas, compression, shocks and phase transitions, by coherent small angle x-ray scattering — ∙Thomas Kluge, Melanie Rödel, Alexander Pelka, Emma McBride, Luke Fletcher, Christian Rödel, Siegfried Glenzer, Michael Buss- mann, Ulrich Schramm, Thomas Cowan P 9.1 Tue 14:30–15:00 b305 Computer simulations of correlated fermions–from quantum plasmas to ultracold atoms and plasma-surface interaction — ∙Michael Bonitz P 13.1 Wed 11:00–11:30 b302 Power exhaust by impurity seeding in fusion reactors — ∙Matthias Bern- ert, Felix Reimold, Arne Kallenbach, Bruce Lipschultz, Ralph Dux, Marco Wischmeier, the ASDEX Upgrade team, the EUROfusion MST1 Team P 17.1 Wed 14:30–15:00 b305 Plasma measurement and control: challenges and recent advances — ∙Timo Gans P 21.1 Thu 11:00–11:30 b302 The behavior of helium in fusion plasmas — ∙Athina Kappatou, Rachael M. -
∫° Plasma Confinement in a Levitated Magnetic Dipole
Plasma Physics Reports, Vol. 23, No. 9, 1997, pp. 742–750. From Fizika Plazmy, Vol. 23, No. 9, 1997, pp. 801–810. Original English Text Copyright © 1997 by Kesner, Mauel. MAGNETIC CONFINEMENT SYSTEMS Plasma Confinement in a Levitated Magnetic Dipole J. Kesner* and M. Mauel** * Massachusetts Institute of Technology, Cambridge, Ma 02129 ** Columbia University, New York, N.Y. 10027 Received April 1, 1995 Abstract—Plasma confinement in the field of a levitated dipole offers many advantages for magnetic fusion. MHD stability is obtained from compressibility which utilizes the large flux tube expansion of a dipole field. Such a device could be high beta, steady state, and exhibit good confinement properties. The large flux expan- sion will ease the difficulty of the divertor design. The configuration is ideal for electron cyclotron heating and controlled convective flow patterns may provide a mechanism for fueling and ash removal. 1. INTRODUCTION tribution function, µ is the adiabatic invariant, µ = The dipole magnetic field is the simplest and most e⊥/2B, J is the parallel invariant, J = °∫v || dl and the flux, common magnetic field configuration in the universe. It ψ is the third adiabatic invariant. The frequencies that is the magnetic far-field of a single, circular current Ω correspond to these invariants are respectively c the loop, and it represents the dominate structure of the cyclotron frequency, ω , the bounce frequency and ω middle magnetospheres of magnetized planets and neu- b d tron stars. The use of a dipole magnetic field generated the curvature driven precessional drift frequency. Both by a levitated ring to confine a hot plasma for fusion of these conditions lead to dipole pressure profiles that scale with radius as r–20/3 while the adiabatic distribu- power generation was first considered by Akira Haseg- µ awa after participating in the Voyager 2 encounter with tion function, F( , J) also implies a density dependence ∝ –4 ∝ –8/3 Uranus [1]. -
Fission and Fusion Can Yield Energy
Nuclear Energy Nuclear energy can also be separated into 2 separate forms: nuclear fission and nuclear fusion. Nuclear fusion is the splitting of large atomic nuclei into smaller elements releasing energy, and nuclear fusion is the joining of two small atomic nuclei into a larger element and in the process releasing energy. The mass of a nucleus is always less than the sum of the individual masses of the protons and neutrons which constitute it. The difference is a measure of the nuclear binding energy which holds the nucleus together (Figure 1). As figures 1 and 2 below show, the energy yield from nuclear fusion is much greater than nuclear fission. Figure 1 2 Nuclear binding energy = ∆mc For the alpha particle ∆m= 0.0304 u which gives a binding energy of 28.3 MeV. (Figure from: http://hyperphysics.phy-astr.gsu.edu/hbase/nucene/nucbin.html ) Fission and fusion can yield energy Figure 2 (Figure from: http://hyperphysics.phy-astr.gsu.edu/hbase/nucene/nucbin.html) Nuclear fission When a neutron is fired at a uranium-235 nucleus, the nucleus captures the neutron. It then splits into two lighter elements and throws off two or three new neutrons (the number of ejected neutrons depends on how the U-235 atom happens to split). The two new atoms then emit gamma radiation as they settle into their new states. (John R. Huizenga, "Nuclear fission", in AccessScience@McGraw-Hill, http://proxy.library.upenn.edu:3725) There are three things about this induced fission process that make it especially interesting: 1) The probability of a U-235 atom capturing a neutron as it passes by is fairly high. -
A 14 Mev Neutron Source Based on Gas Dynamic Trap Concept. Status and Perspectives E.P
30th EPS Conference on Contr. Fusion and Plasma Phys., St. Petersburg, 7-11 July 2003 ECA Vol. 27A, P-2.189 A 14 MeV Neutron Source Based on Gas Dynamic Trap Concept. Status and Perspectives E.P. Kruglyakov, A.A. Ivanov, Yu.A. Tsidulko Budker Institute of Nuclear Physics, 630090, Novosibirsk, Russia Besides the main physical problems of controlled fusion such as physics of alpha particles, ignition, etc, there exists a problem of a limited lifetime of structural materials under intensive bombardment by 14 MeV neutrons, degradations of their electrical and mechanical properties, accumulation of impurities, etc. At present, the development of the world fusion program is concentrated on the ITER project. However, even in the case of success of this project it cannot serve a function of high power neutron source for candidate material tests for future fusion power plant because of low fluence. Indeed, irradiation of one of the existing candidates on the role of a material for the first wall (ferritic-martensitic steel) with 14 MeV neutron flux of order of 2 MW/m2 during 10 years will lead to the level of radiation damages of 200 dpa. The ITER will provide only about 2 dpa per year. Thus, the fusion reactor cannot be built without performing extensive program dedicated to qualify the materials to be used in the reactor core under high level irradiation by 14 MeV and secondary neutrons. In other words, the final goal of the controlled fusion program can not be achieved without urgent design and construction of a dedicated high power 14 MeV neutron source (NS).