DOCSLIB.ORG

Princeton University Plasma Physics Laboratory Princeton, New Jersey

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
Princeton University Plasma Physics Laboratory Princeton, New Jersey PPPL-Q--42 DE86 008595 Annual Report Covering the Period October 1. 1983 to September 30. 1984 Princeton University Plasma Physics Laboratory Princeton, New Jersey PPPL-Q-42 Edited by Carol A. Phillips DISCLAIMER This report was prepared as an account of work sponsored by an agency or the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsi­ bility 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. Refer­ ence herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recom­ mendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. Unless otherwise designated, the work in this report is funded by the United States Department of Energy under Contract DE-AC02-76-CHO- 3073. Printed in the United States of America1 *» vV •J SSTRIBUTieS CF THiS atCUffltRT JS tm££TO CONTENTS Preface 1 Principal Parameters Achieved in Experimental Devices 3 Tokamak Fusion Test Reactor 5 Princeton Large Torus 31 Princeton Beta Experiment 40 S-1 Spheromak 51 Advanced Concepts Torus-I 55 X-Ray Laser Studies 58 Theory 63 Tokamak Modeling 69 Reactor Studies 73 Spin-Polarized Fusion Program 75 Tokamak Fusion Core Experiment 77 Engineering Department 80 Project Planning and Safety Office 95 Quality Assurance and Reliability 98 Administrative Operations 99 PPPL Invention Disclosures for Fiscal Year 1984 109 Graduate Education: Plasma Physics 111 Graduate Education: Plasma Science and Fusion Reactor Technology 114 Section Coordinators 119 Glossary of Abbreviations, Acronyms, Symbols 120 PREFACE During FY84, experimental research on the device, with a resultant improvement in plasma Tokamak Fusion Test Reactor (TFTR) confirmed parameters. A promising new ICRF-type heating the favorable size-scaling of energy confinement technique, based on the ion Bernstein wave, was in large ohmic-hoated tokamak plasmas. Initial developed on the Advanced Concepts Torus auxiliary-heating studies were carried out with (ACT-I). neutral-beam injection and adiabatic compres­ The single-pass gain in the Soft X-Ray Laser sion. Substantial progress was also made Experiment has been advanced to 6.5 (corre­ towards full-parameter machine operation and sponding to a level of stimulated emission 100 towards the development of technical capabilities times larger than spontaneous emission) for the for the deuterium-deuterium and deuterium- 182- A line of a carbon plasma. A small experiment tritium O ~ 1 experiments. on the spin-polarization of hydrogen, which is The Princeton Large Torus (PLT) extended its aimed at investigating the prospects tor polarized ion cyclotron range of frequencies (ICRF) heating fusion-reactor plasmas, has reached the 28% experiments to the 4-MW power level, producing polarization level in atomic hydrogen of 1012 cm-3 ion temperatures above 4 keV. Lower-hybrid density. current drive was advanced to plasma regimes Theoretical studies in the area of lower-hybrid- in the 1013 cm-3 density range, by means of a driven current ramp-up have produced remark­ new 2.45-MHz source. The problem of intense ably detailed agreement with the PLT experiments. focal Iimiter heating during long-pulse radio- New predictive capabilities for MHD stability and frequency discharges was addressed success­ transport have been developed in supportof'two- fully by introduction of a rotating limiter system. dimensional" experiments, such as the PBX and The reconfiguration of the Poloidal Divertor S-1, as well as advanced "three-dimensional" Experiment (PDX) into the Princeton Beta concepts, such as the Heliac h igh-beta stellarator. Experiment (PBX) resulted in a doubling of the Sophisticated new codes are also L-Jing devel­ achievable beta value: stable tokamak plasmas oped to treat edge-plasma phenomena and with average /3's above 5% werp reached for the atomic effects in the vicinity of lokamak divertors first lime. The bean-shaped tokamak was found and limiters. to enter readily into the favorable H- mode plasma- The national design effort in support of a confinement regime. Tokamak Fusion Core Experiment (TFCX), which The predicted stabilization of spheromak was coordinated by PPPL, led to the publication plasmas by means of external figure-eight coils of a TFCX Preconceptual Design Report in July, was demonstrated successfully on the S-1 1984. PRINCIPAL PARAMETERS ACHIEVED IN EXPERIMENTAL DEVICES (Fiscal Year 1984} Ar-mate Parameters Tokamak Facilities Concept Facilities TFTH PBX PLT S-1 ACT-I R<m) 2.56 1.45 1.32 0.40 0.59 a Cm) 0.82 0.4 0.42 0.25 0.1 Ip <MA) 1.5 0.5 0.7 0.4 — BT(T) 3.9 1.0 3.3 0.4 0.57 TAUX (sec) 0.5 0.3 0.3 — dc PAUX (MW) NB 1.5, (80keV) 7, (50 keV) 1.5, (40 keV) — — ICRF — — 4.0, (30 MHz) — 0.002 LH 0.6, (600 MHz) 0.2 " ~ 0.6, (2.45 GHz) n(0) (cm-3)* 0.6 x 10"" 10"4 0.8xl0"i 3x io14 3x101 T(0) (keV)* 3.5 4.0 4.0 0.06 0.04 TE (msec)* 300 40 40 0.25 0.2 "These highest values of n, T. and T were not achieved simultaneously. TOKAMAK FUSION TEST REACTOR During the first full year of experimental operations bearing runout problems, so that TFTR now has an (FY84), a very considerable effort continued on Ihe operational pulsed-power capability of 950 MVA with fabrication, installation, and commissioning of 4500 MJ of deliverable energy. This was a major neutral-beam systems, on the high-power-capability milestone for the project. internal armor, and on the addition of increasingly The 1984 spring shutdown was carried out sophisticated diagnostics. Major efforts also con­ according to plan. Major activities included instal­ tinued towards providing downstream capability in lation of two neutral beamlines and the addition of the areas of tritium systems, remote handling, and prototype protective armor to the inside o) the vacuum shielding. Progress in all these areas is reported in vessel. All shutdown tasks were completed on detail in the following sections and briefly summarized schedule, and the vacuum vessel was pumped down here. at the end of April. After a series of power tests and Figure 1 illustrates the division of the available several weeks of pulse-discharge cleaning, normal operating time among the various activities. As the high-power operation resumed in June. Tokamak Fusion Test Reactor <TFTR) gradually In this first full year of TFTR experimental operation, assumes its final form, machine availability for there was significant progress on experimental experimental operations is rising steadily towards studies of confinement during ohmic heating and levels equal to or exceeding those anticipated at the plasma compression, as well as on initial experiments time of design authorization. using neutral-beam heating. In addition, a review of the projections for TFTR Q ~ 1 capability was carried ou;. Planning activities for pellet injection and lower- Tr'TR OPERATIONS IFY-BI] hybrid current drive were also initiated. PaljmqW.m Sj The TFTR-ORNL (Oak Ridge National Laboratory) NrulrCl Btfims collaboration began during the summer of 1984. The ten on-site ORNL-ISX. (Impurity Study Experiment) physicists immediately began to make important contributions to the TFTR Project. Cumas s t 8S s The TFTR was operated at plasma currents up to P6.I.T,,., ^ S g S ^ lp= 1.4 MA, toroidal fields up to Bp = 2.7 T. and plasma durations up to 4 sec. As indicated in Fig. 1, there N. <K» ^ g 5 B were two major operational periods, a winter 1983- 1984 run period and a summer 1984 run period. The conditioning lor the summer 1984 run period involved a two-week bakeout of the entire torus, including the HjhdO, I S S ! pumping ducts, at 150°C. While the vessel was hot, 50 hours of glow-discharge cleaning (p = 0.7 Pa, I OCT MOV DEC JM FEB VflR 3PH MflV JUtl JUL QUO SEP OCT '83 "ea = 15 A) and 70 hours (45,000 pulses) of pulse- discharge cleaning were performed. For the winter Fig. 7. Division ot available lime tor various activities. 1983-1984 run period. 1he graphite movable limiter (85X3065) was coated with TiC (titanium carbon). Titanium was the major metallic impurity, with a relative concen­ 3 During 19B4, the TFTR Facility continued to extend tration of nji/ne as high as 5 x 10- in low-density its operating capability towards design-rated param­ plasmas. Because of difficulties with the adhesion, eters. The toroidal-field (TF) coil system was tested the TiC coating was removed during the shutdown and now operates routinely at 56 kA (4.0 T). The power period. With the TiC removed, the titanium impurity supplies are ready to support full-field (73 kA, radiation was reduced by a factor of 40. The nickel, 5.2 T) integrated system tests. The ohmic-heating coil from the Inconel inner-wall limiter, increased circuit was operated at full current in both mode A modestly. However, all the metallic impurities (24 kA) and mode B (20 kA). During this period, the decreased substantially at higher densities. Beth X- interrupter mode of operation was successfully ray pulse-height analysis and visible bremsstrahlung commissioned, resulting in a large increase in measurements indicate a significant reduction in ZeH available volt-seconds, and the equilibrium-field (EF) at low densities with the removal of the TiC coating.
Load more

Recommended publications
  • A European Success Story the Joint European Torus
    EFDA JET JETJETJET LEAD ING DEVICE FOR FUSION STUDIES HOLDER OF THE WORLD RECORD OF FUSION POWER PRODUCTION EXPERIMENTS STRONGLY FOCUSSED ON THE PREPARATION FOR ITER EXPERIMENTAL DEVICE USED UNDER THE EUROPEAN FUSION DEVELOPEMENT AGREEMENT THE JOINT EUROPEAN TORUS A EUROPEAN SUCCESS STORY EFDA Fusion: the Energy of the Sun If the temperature of a gas is raised above 10,000 °C virtually all of the atoms become ionised and electrons separate from their nuclei. The result is a complete mix of electrons and ions with the sum of all charges being very close to zero as only small charge imbalance is allowed. Thus, the ionised gas remains almost neutral throughout. This constitutes a fourth state of matter called plasma, with a wide range of unique features. D Deuterium 3He Helium 3 The sun, and similar stars, are sphe- Fusion D T Tritium res of plasma composed mainly of Li Lithium hydrogen. The high temperature, 4He Helium 4 3He Energy U Uranium around 15 million °C, is necessary released for the pressure of the plasma to in Fusion T balance the inward gravitational for- ces. Under these conditions it is pos- Li Fission sible for hydrogen nuclei to fuse together and release energy. Nuclear binding energy In a terrestrial system the aim is to 4He U produce the ‘easiest’ fusion reaction Energy released using deuterium and tritium. Even in fission then the rate of fusion reactions becomes large enough only at high JG97.362/4c Atomic mass particle energy. Therefore, when the Dn required nuclear reactions result from the thermal motions of the nuclei, so-called thermonuclear fusion, it is necessary to achieve u • extremely high temperatures, of at least 100 million °C.
    [Show full text]
  • Fusion: the Way Ahead
    Fusion: the way ahead Feature: Physics World March 2006 pages 20 - 26 The recent decision to build the world's largest fusion experiment - ITER - in France has thrown down the gauntlet to fusion researchers worldwide. Richard Pitts, Richard Buttery and Simon Pinches describe how the Joint European Torus in the UK is playing a key role in ensuring ITER will demonstrate the reality of fusion power At a Glance: Fusion power • Fusion is the process whereby two light nuclei bind to form a heavier nucleus with the release of energy • Harnessing fusion on Earth via deuterium and tritium reactions would lead to an environmentally friendly and almost limitless energy source • One promising route to fusion power is to magnetically confine a hot, dense plasma inside a doughnut-shaped device called a tokamak • The JET tokamak provides a vital testing ground for understanding the physics and technologies necessary for an eventual fusion reactor • ITER is due to power up in 2016 and will be the next step towards a demonstration fusion power plant, which could be operational by 2035 By 2025 the Earth's population is predicted to reach eight billion. By the turn of the next century it could be as many as 12 billion. Even if the industrialized nations find a way to reduce their energy consumption, this unprecedented increase in population - coupled with rising prosperity in the developing world - will place huge demands on global energy supplies. As our primary sources of energy - fossil fuels - begin to run out, and burning them causes increasing environmental concerns, the human race faces the challenge of finding new energy sources.
    [Show full text]
  • DISTRIBUTION of THIS DOCUMENT IS UNLIMITED Temperatures in the Range 5-10 Kev Are Still Needed, but the Lawson Number Can Be Reduced to the Low 10 Cm Sec Range
    TFTR and Other Large Tokamaks Plasma Physics Laboratory, Princeton University Princeton, New Jersey 08544 H.P. Furth CONF-8604223—1 DE86 012761 Introduction The near-term goal of fusion research is to produce deuterium-tritium plasmas with temperatures above 10 keV and Lawson numbers nTE above 10 cm sec. As indicated in Fig. 1, experiments entering this parameter range will be able to satisfy Lawson's break-even criterion, where the fusion power output equals the required plasma-heating-power input (Q = 1 ). The ultimate reactor goal is to reach equilibrium-burn conditions, where the energetic alpha particles generated by the D-T reaction are sufficient to maintain the plasma temperature against all heat losses (Q = °°). At the outset of the international controlled-fusion research effort in the 19 50's, Lawson's goal seemed intimidatingly remote from experimental capabilities. During the following ten years, substantial scientific progress was made, but the rate of advance in the Lawson diagram was not such as to inspire confidence that the fusion program would reach fruition within the lifetime of its pioneers. The notable success of the Kurchatov Institute's T-3 tokamak during 1968-69 brightened the outlook considerably. The tokamak configuration was recognized as a cost-effective experimental tool and has permitted steady progress during subsequent decades. World-wide recognition of the favorable experimental opportunity for entry into the reactor plasma regime led to the initiation, in the mid-1970's, of four large new tokamak projects (Table I). Plans for the Joint European Torus (JET) were defined in 1971-73: th_ very large plasma size and high current of the JET plasma offered a potential for exceeding the Lawson break- even criterion and possibly evan reaching ignition in D-T plasmas.
    [Show full text]
  • Corrosion Issues in Fusion Reactors
    Corrosion Issues in Fusion Reactors Digby D. Macdonald1 and George R. Engelhardt2 1Department of Nuclear Engineering University of California at Berkeley Berkeley, CA 94720 2OLI Systems, Inc. 240 Cedar Knolls Rd Cedar Knolls, NJ 07927 WCO Forum Corrosion 2020 Houston, TX, USA Background • Nuclear fusion is the process of fusing the light elements (primarily 1 2 3 the isotopes of hydrogen, H1, D1, T1. • Fusion results in a loss of mass, which is converted into energy, E = Δm.c2. • Process that occurs in the sun and stars in nuclear synthesis. Minimum temperature for D + T is 10 keV = 300,000,000 oC equivalent. • First demonstrated on earth in 1950s through thermonuclear weapons. • Almost a limitless source of clean energy if it can be made to work. • First controlled fusion demonstrated at JET in Oxford, UK, Q =0.75. • First technology demonstration, ITER (‘the way”), being constructed at Cadarache, France. Q > 10. Thermonuclear Reactions Reaction Reaction Equation Initial Mass (u) Mass Change (u) % Mass Change 2 2 3 1 -3 D-D D1 + D1 → He2 + n0 4.027106424 -2.44152x10 0.06062 2 2 3 1 -3 D-D D1 + D1 → H1 + p1 4.027106424 -3.780754x10 0.09388 2 3 4 1 D-T D1 + T1 → He2 + n0 5.029602412 -0.019427508 0.3863 e--p+ e- + p+ → 2hν 1.8219x10-31 -1.8219x10-31 100 Must overcome Coulombic repulsion of nuclei in the plasma Preferred Reaction • The easiest reaction to achieve 2 3 4 1 is: D1 + T1 → He2 + n0 because it has the lowest ignition temperature (10 keV).
    [Show full text]
  • June 2018 Fusion in Europe
    FUSION IN EUROPE NEWS & VIEWS ON THE PROGRESS OF FUSION RESEARCH “Let us face it: TO DTT OR NOT TO DTT there is no VACUUM – HOW NOTHING REALLY planet B!” MATTERS NOW IS THE TIME TO BE AT JET 2 2018 Fusion Writers … wanted! … and Artists This could be you Fusion in Europe is call- ing for aspiring writers and gifted artists! Introduce yourself to an international audience! Catch one of our topics and turn it into your own! • The future powered by fusion energy • Fusion science and industrial reality • Fusion - a melting pot of different sciences • Fusion drives innovation Find the entire list here: tinyurl.com/ybd4omz7 Your application should include a short CV and a motivational letter. Please apply here: tinyurl.com/ybd4omz7 EUROfusion | Communications Team | Anne Purschwitz (”Fusion in Europe“ Editor) Boltzmannstr. 2 | 85748Application Garching | +49 89 deadline: 3299 4128 | [email protected] 25 June 2018 | Editorial | EUROfusion | “It is the best time to be at JET right now” says a passionate Eva Belo nohy. The member of JET’s Exploitation Unit has recently organised a very suc- cessful workshop. It was aimed to ‘refresh’ the knowledge of European fu- sion researchers regarding the Joint European Torus (JET) but that was a classic understatement. The meeting was a fully-fledged overview on JET’s capabilities which have tremendously changed in the past. The tokamak has gone through major upgrades since it saw its first deuterium tritium campaign in 1997. Those include not only an ITER-like wall but also an Fusion Writers… wanted! … increase of the heating power by 50 percent.
    [Show full text]
  • Introduction to Nuclear Fusion
    Introduction to Nuclear Fusion Prof. Dr. Yong-Su Na To build a sun on earth - Open magnetic confinement - Closed magnetic confinement 2 What is closed magnetic confinement? 3 Open Magnetic System B sin 2 min Bmax v|| loss cone loss cone - Suffering from end losses J.P. Freidberg, “Ideal Magneto-Hydro-Dynamics”, lecture note A. A. Harms et al, “Principles of Fusion Energy”, World Scientific (2000) 4 Open Magnetic System Magnetic field Is this motion realistic? ion Dunkin donuts (2010) 5 Closed Magnetic System Magnetic field Donut-shaped vacuum vessel ion 6 Closed Magnetic System 7 Closed Magnetic System Magnetic field R 0 a Plasma needs to be confined ion R0 = 1.8 m, a = 0.5 m in KSTAR 8 Closed Magnetic System Magnetic field R 0 a Plasma needs to be confined ion R0 = 6.2 m, a = 2.0 m in ITER 9 Closed Magnetic System Toroidal Field (TF) coil Magnetic field Toroidal direction Applying toroidal magnetic field ion 3.5 T in KSTAR, 5.3 T in ITER 10 Closed Magnetic System Toroidal Field (TF) coil Toroidal direction Applying toroidal magnetic field 3.5 T in KSTAR, 5.3 T in ITER 11 Closed Magnetic System Toroidal Field (TF) coil Magnetic field Toroidal direction Magnetic field of earth? 0.5 Gauss = 0.00005 T ion 12 http://www.crystalinks.com/earthsmagneticfield.html Closed Magnetic System Magnetic field Magnetic field of earth? 0.5 Gauss = 0.00005 T ion http://www.transformacionconciencia.com/archives/2384 13 Closed Magnetic System Magnetic field ion 14 Lesch, Astrophysics, IPP Summer School (2008) Closed Magnetic System Magnetic field ion electron
    [Show full text]
  • Neutron Emission Spectrometry for Fusion Reactor Diagnosis
    Digital Comprehensive Summaries of Uppsala Dissertations from the Faculty of Science and Technology 1244 Neutron Emission Spectrometry for Fusion Reactor Diagnosis Method Development and Data Analysis JACOB ERIKSSON ACTA UNIVERSITATIS UPSALIENSIS ISSN 1651-6214 ISBN 978-91-554-9217-5 UPPSALA urn:nbn:se:uu:diva-247994 2015 Dissertation presented at Uppsala University to be publicly examined in Polhemsalen, Ångströmlaboratoriet, Lägerhyddsvägen 1, Uppsala, Friday, 22 May 2015 at 09:15 for the degree of Doctor of Philosophy. The examination will be conducted in English. Faculty examiner: Dr Andreas Dinklage (Max-Planck-Institut für Plasmaphysik, Greifswald, Germany). Abstract Eriksson, J. 2015. Neutron Emission Spectrometry for Fusion Reactor Diagnosis. Method Development and Data Analysis. Digital Comprehensive Summaries of Uppsala Dissertations from the Faculty of Science and Technology 1244. 92 pp. Uppsala: Acta Universitatis Upsaliensis. ISBN 978-91-554-9217-5. It is possible to obtain information about various properties of the fuel ions deuterium (D) and tritium (T) in a fusion plasma by measuring the neutron emission from the plasma. Neutrons are produced in fusion reactions between the fuel ions, which means that the intensity and energy spectrum of the emitted neutrons are related to the densities and velocity distributions of these ions. This thesis describes different methods for analyzing data from fusion neutron measurements. The main focus is on neutron spectrometry measurements, using data used collected at the tokamak fusion reactor JET in England. Several neutron spectrometers are installed at JET, including the time-of-flight spectrometer TOFOR and the magnetic proton recoil (MPRu) spectrometer. Part of the work is concerned with the calculation of neutron spectra from given fuel ion distributions.
    [Show full text]
  • Plasma Physics Laboratory
    fco^m OCTOBER 1980 UC-20b,d NON-SUPERCONDUCTING- MAGNET STRUCTURES FOR NEAR^TEfti LARGE FUSION EXPERIMENTAL DEVICES -:BY J. FILE, D. S, KHUT^xiU, R, E, MARINO, AND G. ti, RAPPE PLASMA PHYSICS LABORATORY r,7 PRINCETON UNIVERSITY PRINCETON, NEW JERSEY m tr T;;;S 30CUV£MT !S iHnwrru NON-SUPERCONDUCTING MAGNET STRUCTURES FOR NBRR-'IERM, LARGE FUSION EXPERIMENTAL DEVICES J. File, D.S. Knutson, R.E. Marino and G.H. Rappe Plasma Physics Laboratory, Princeton University, Princeton, New Jersey 08544, USA ABSTRACT Water cooled copper magnets provide a means of producing high magnetic fields for tokamaks using a well developed existing technology. The basic function of these magnets is to provide reliable, both time varying and steady state, magnetic fields. Copper electrical properties, insulation, and water cooling systems play major roles in design selection. Aside from being electro-magnetic devices, coils designed for tokamaks must be self-supporting structures, capable of resisting large I x B magnetic forces. These magnets require the integration of both electrical and structural design considerations. Magnet integrity is enhanced by the presence of structures which lend additional external support. These external structural systems are highly stressed and, often, deflection limited. This paper describes the magnet and structural design in the following American tokamak devices: the Princeton Large Torus (PLT), the Princeton Divertor Experiment (PDX), and the Tokamak Fusion Test Reactor (TFTR). The Joint European Torus (JET), also presented herein, has a magnet structure evolved from several European programs and, like TFTR, represents state of the art magnet and structure design. | DISCLAIMER TliTtbOGknA!}!K>£!K!ajn*^oun1i''M?l looniofeo cyan Jgency of fifl Unrie-J Slaftt Gowmrien*.
    [Show full text]
  • Fusion-The-Energy-Of-The-Universe
    Fusion The Energy of the Universe WHAT IS THE COMPLEMENTARY SCIENCE SERIES? We hope you enjoy this book. If you would like to read other quality science books with a similar orientation see the order form and reproductions of the front and back covers of other books in the series at the end of this book. The Complementary Science Series is an introductory, interdisciplinary, and relatively inexpensive series of paperbacks for science enthusiasts. The series covers core subjects in chemistry, physics, and biological sciences but often from an interdisciplinary perspective. They are deliberately unburdened by excessive pedagogy, which is distracting to many readers, and avoid the often plodding treatment in many textbooks. These titles cover topics that are particularly appropriate for self-study although they are often used as complementary texts to supplement standard discussion in textbooks. Many are available as examination copies to professors teaching appropriate courses. The series was conceived to fill the gaps in the literature between conventional textbooks and monographs by providing real science at an accessible level, with minimal prerequisites so that students at all stages can have expert insight into important and foundational aspects of current scientific thinking. Many of these titles have strong interdisciplinary appeal and all have a place on the bookshelves of literate laypersons. Potentialauthorsareinvitedtocontactoureditorialoffice: [email protected]. Feedback on the titles is welcome. Titles in the Complementary Science Series are detailed at the end of these pages. A 15% discount is available (to owners of this edition) on other books in this series—see order form at the back of this book.
    [Show full text]
  • Sixty Years on from ZETA …
    Sixty years on from ZETA … Chris Warrick The Sun … What is powering it? Coal? Lifetime 3,000 years Gravitational Energy? Lifetime 30 million years – Herman Von Helmholtz, Lord Kelvin - mid 1800s The Sun … Suggested the Earth is at least 300 million years old – confirmed by geologists studying rock formations … The Sun … Albert Einstein (Theory of Special Relativity) and Becquerel / Curie’s work on radioactivity – suggested radioactive decay may be the answer … But the Sun comprises hydrogen … The Sun … Arthur Eddington proposed that fusion of hydrogen to make helium must be powering the Sun “If, indeed, the subatomic energy is being freely used to maintain their great furnaces, it seems to bring a little nearer to fulfilment our dream of controlling this latent power for the well-being of the human race – or for its suicide” Cambridge – 1930s Cockcroft Walton accelerator, Cavendish Laboratory, Cambridge. But huge energy losses and low collisionality Ernest Rutherford : “The energy produced by the breaking down of the atom is a very poor kind of thing . Anyone who expects a source of power from the transformation of these atoms is talking moonshine.” Oxford – 1940s Peter Thonemann – Clarendon Laboratory, Oxford. ‘Pinch’ experiment in glass, then copper tori. First real experiments in sustaining plasma and magnetically controlling them. Imperial College – 1940s George Thomson / Alan Ware – Imperial College London then Aldermaston. Also pinch experiments, but instabilities started to be observed – especially the rapidly growing kink instability. AERE Harwell Atomic Energy Research Establishment (AERE) Harwell – Hangar 7 picked up fusion research. Fusion is now classified. Kurchatov visit 1956 ZETA ZETA Zero Energy Thermonuclear Apparatus Pinch experiment – but with added toroidal field to help with instabilities and pulsed DC power supplies.
    [Show full text]
  • Plasma Physics and Controlled Fusion Research During Half a Century Bo Lehnert
    SE0100262 TRITA-A Report ISSN 1102-2051 VETENSKAP OCH ISRN KTH/ALF/--01/4--SE IONST KTH Plasma Physics and Controlled Fusion Research During Half a Century Bo Lehnert 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-2001-04 ISRN KTH/ALF/--01/4--SE Plasma Physics and Controlled Fusion Research During Half a Century Bo Lehnert 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 PLASMA PHYSICS AND CONTROLLED FUSION RESEARCH DURING HALF A CENTURY Bo Lehnert Alfven Laboratory, Royal Institute of Technology S-100 44 Stockholm, Sweden ABSTRACT A review is given on the historical development of research on plasma physics and controlled fusion. The potentialities are outlined for fusion of light atomic nuclei, with respect to the available energy resources and the environmental properties. Various approaches in the research on controlled fusion are further described, as well as the present state of investigation and future perspectives, being based on the use of a hot plasma in a fusion reactor. Special reference is given to the part of this work which has been conducted in Sweden, merely to identify its place within the general historical development. Considerable progress has been made in fusion research during the last decades.
    [Show full text]
  • The US and the International Quest for Fusion Energy
    Chapter 4 Fusion Science and Technology Chapter 4 Fusion Science and Technology Great progress has been made over the past for lack of funds; science had a higher funding 35 years of fusion research. Nevertheless, many priority. In addition, fusion technologies that re- scientific and technological issues have yet to be quire a source of fusion power to be tested and resolved before fusion reactors can be designed developed have had to await a device that could and built. Fundamental questions in plasma sci- supply the power. Until recently, the fusion sci- ence remain, especially involving the behavior ence database has not been sufficient to permit of plasmas that actually produce fusion power. such a device to be designed with confidence. Other plasma science questions involve the be- This chapter discusses the various confinement havior and operation of the various confinement concepts under study, the systems required in a concepts that might be used to hold fusion fusion reactor, and the issues that must be re- plasmas. solved before such systems can be built. It then To date, engineering issues have not been stud- outlines the research plan required to resolve ied as extensively as plasma science issues. For these issues and estimates the amount of time and many years, engineering studies were deferred money that such a research plan will take. CONFINEMENT CONCEPTS’ Most of the fusion program’s research has fo- Table 4-1 lists the principal confinement schemes cused on different magnetic confinement con- presently under investigation in the United States cepts that can be used to create, confine, and and classifies them according to their level of de- understand the behavior of plasmas.
    [Show full text]