Catastrophes in the Elmo Bumpy Torus
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1 Looking Back at Half a Century of Fusion Research Association Euratom-CEA, Centre De
Looking Back at Half a Century of Fusion Research P. STOTT Association Euratom-CEA, Centre de Cadarache, 13108 Saint Paul lez Durance, France. This article gives a short overview of the origins of nuclear fusion and of its development as a potential source of terrestrial energy. 1 Introduction A hundred years ago, at the dawn of the twentieth century, physicists did not understand the source of the Sun‘s energy. Although classical physics had made major advances during the nineteenth century and many people thought that there was little of the physical sciences left to be discovered, they could not explain how the Sun could continue to radiate energy, apparently indefinitely. The law of energy conservation required that there must be an internal energy source equal to that radiated from the Sun‘s surface but the only substantial sources of energy known at that time were wood or coal. The mass of the Sun and the rate at which it radiated energy were known and it was easy to show that if the Sun had started off as a solid lump of coal it would have burnt out in a few thousand years. It was clear that this was much too shortœœthe Sun had to be older than the Earth and, although there was much controversy about the age of the Earth, it was clear that it had to be older than a few thousand years. The realization that the source of energy in the Sun and stars is due to nuclear fusion followed three main steps in the development of science. -
Simulation of a High Speed Counting System for Sic Neutron
Transactions of the Korean Nuclear Society Spring Meeting Jeju, Korea, May 17-18, 2018 Analysis of Technical Issues for Development of Fusion-Fission Hybrid Reactor (FFHR) Doo-Hee Chang Nuclear Fusion Technology Development Division, Korea Atomic Energy Research Institute, Daejeon 34057, Korea *Corresponding author: [email protected] 1. Introduction • ~100 tokamaks in the worldwide since 1957 • Physics performance parameters achieved at or near The nuclear fission reactors remain public concerns lower limit of reactor relevance about the safety, waste and decommissioning • Large, world‐wide physics and technology (afterwards) that they produce. The most optimistic programs supporting ITER (initial operation in assessment predicts that fusion technology will not be 2025, but possible delay again) able to produce electricity on a commercial scale for at • ITER will achieve reactor‐relevant physics and least another four decades. There is a third nuclear technology parameters simultaneously, produce option led to a resurgence of interest, which combines 500 MWth and investigate very long‐pulse the aspects of fission and fusion technologies in the operation form of the fusion-fission hybrid reactor (FFHR) [1]. An (b) Many other confinement concepts (e.g. mirror, FFHR is a fusion reactor surrounded by a fission bumpy torus) have fallen by the wayside or remain blanket, containing the thorium, uranium, and on the backburner transuranic (TRU) elements, to increase output power, (c) A few other confinement concepts (e.g. stellarator, to breed -
Experimental Study of Equilibrium in a Bumpy Torus
x - .2. v 7 .d>. oml 0RNL/TM-9520 Experimental Study of Equilibrium in a Bumpy Torus S. Hiroe J. A. Cobble R. J. Colchin G. L. Chen K. A. Connor J. R. Goyer L. Solensten 5; ',•-•• i ' i P DISTRIBUTION OF THIS DOCUMENT IS UNUIftTTEB ORNL/TM—9520 DE86 014415 Pist. cH^W^O f,g Fusion Energy Division Experimental Study of Equilibrium in a Bumpy Torus S. Hiroe J. A. Cobble R. J. Colchin G. L. Chen Fusion Energy Division K. A. Connor, J. R. Goyer, L. Solensten Rensselaer Polytechnic Institute Troy, New York Date of Issue: June 1986 Prepared by the OAK RIDGE NATIONAL I-ABORAI OKY Oak Ridge, Tennessee 37831 operated by <lkT_ MARTIN MARIETTA ENERGY SYSTEMS, INC. for the U. S. DEPARTMENT OF KNKRGY under Contract No. DE-AC05-840R21400 OlSTRlBUT,0«0FTHlSD0CU^T^^ CONTENTS ABSTRACT v I. INTRODUCTION 1 n. EXPERIMENTAL RESULTS 3 m. DISCUSSION 15 A. Formation of closed potential contours 15 B. Inward displacement of potential contours 22 C. Electrostatic beta limit 26 D. Force balance 28 E. Explanation of potential deformation 33 TV. CONCLUSION 37 ACKNOWLEDGMENTS 39 REFERENCES 41 iii ABSTRACT Plasma equilibrium in the ELMO Bumpy Torus (EBT)1 was studied experimentally by measurements of the electrostatic potential structure. Before an electron tail population is formed, the electric field is found, roughly speaking, to be in the vertical direction. The appearance of a high-energy electron tail signals the formation of a negative potential well, and the potential contours start to nest. The potential contours are shifted inward with respect to the center of the conducting wall. -
Introduction to Fusion Energy Plasma Physics (K
BOOK REVIEWS S',".'"" o book, tor review " based on the editor's 'P'"'""' ",,,d'", possible reader E interest and on the availability of the book to the editor. Occasional selections may include II. L><:5.NB; ns books on topics somewhat peripheral to the subject matter ordinarily considered acceptable. 1111. Controlled Nuclear Fusion - Fundamentals of Its experiments and design studies have evidently so consumed Utilization for Energy Supply the time of experienced workers that there is a great short age of rigorous but comprehensible review articles that Authors J. Raeder, K. Borass, R. Bunde, W. should serve as the basis for such a text. Danner, R. Klingelhofer, L. Lengyel, In summary, the book by Raeder et al. should serve as F. Leuterer, M. Soli a useful supplementary text for courses on controlled fusion and a useful enough reference to justify its purchase by Publisher John Wiley & Sons, Inc., Somerset, researchers and instructors active in the various fields of New Jersey (1986) tokamak research that it covers. Despite the recent publica tion of a number of very good efforts, the definitive, self Pages 316 (illustrated) contained, introductory text on fusion reactor design and a more widely useful reference work for tokamak researchers Price $100.00 remain to be written. Clifford E. Singer Reviewer Clifford E. Singer received his PhD at the University of California, Berkeley. He has worked on the theory and This book is a translation of Kontrol/ierte Kernfusion, applied physics ofplasma transport in tokamak experiments written in 1980. Despite the delay in translation, the book and reactors at Princeton Plasma Physics Laboratory (and remains a timely summary of many aspects of tokamak the University ofIllinois) since 1977. -
CA ^ F FILE ^N^ ^Q? MBI II Bhb •*• INITIAL RESULTS from the NASA LEWIS BUMPY TOR US EXPERIMENT
https://ntrs.nasa.gov/search.jsp?R=19740002565 2020-03-23T13:57:37+00:00Z 7 4 10678 NASA TECHNICAL NASA TM X-71468 MEMORANDUM oo ! i—i f 7 ^nA^ ^Q^ ? FMB I FILI I BhBE •*• X C g COPY < < INITIAL RESULTS FROM THE NASA LEWIS BUMPY TOR US EXPERIMENT by J. Reece Roth, Richard W. Richardson, and Glenn A. Gerdin Lewis Research Center Cleveland, Ohio 44135 ;!' TECHNICAL PAPER proposed for presentation at Annual Meeting of the Plasma 1r Physics Division of the American Physical Society Philadelphia, Pennsylvania, August 31 - November 3, 1973 INITIAL RESULTS FROM THE NASA LEWIS BUMPY TORUS EXPERIMENT BY J. REECE ROTH, RICHARD W. RICHARDSON*, AND GLENN A. GERDIN* CD £ NASA LEWIS RESEARCH CENTER t-i- CLEVELAND,: OHIO ABSTRACT Initial results have been obtained from low power operation of the NASA i Lewis Bumpy Torus experiment, in which a steady-state ion heating method based on the modified Penning discharge is applied in a bumpy torus confinement geometry. The magnet facility consists of 12 superconducting coils, each 19 cm i.d. and capable of 3.0 T, equally spaced in a toroidal array 1.52 m in major diameter. A 18 cm i.d. anode ring is located at each of the 12 midplanes and is maintained at high positive potentials by a dc power supply. Initial observations indicate electron temperatures from 10 to 150 eV, and ion kinetic temperatures from 200 eV to 1200 eV. Two modes of operation are observed, which depend on background pressure, and have different radial density profiles, Steady state neutron production has been observed. -
Selection of a Toroidal Fusion Reactor Concept for a Magnetic Fusion Production Reactor 1
Journal of Fusion Energy, Vol. 6, No. 1, 1987 Selection of a Toroidal Fusion Reactor Concept for a Magnetic Fusion Production Reactor 1 D. L. Jassby 2 The basic fusion driver requirements of a toroidal materials production reactor are consid- ered. The tokamak, stellarator, bumpy torus, and reversed-field pinch are compared with regard to their demonstrated performance, probable near-term development, and potential advantages and disadvantages if used as reactors for materials production. Of the candidate fusion drivers, the tokamak is determined to be the most viable for a near-term production reactor. Four tokamak reactor concepts (TORFA/FED-R, AFTR/ZEPHYR, Riggatron, and Superconducting Coil) of approximately 500-MW fusion power are compared with regard to their demands on plasma performance, required fusion technology development, and blanket configuration characteristics. Because of its relatively moderate requirements on fusion plasma physics and technology development, as well as its superior configuration of production blankets, the TORFA/FED-R type of reactor operating with a fusion power gain of about 3 is found to be the most suitable tokamak candidate for implementation as a near-term production reactor. KEY WORDS: Magnetic fusion production reactor; tritium production; fusion breeder; toroidal fusion reactor. 1. STUDY OBJECTIVES Section 2 of this paper establishes the basic requirements that the fusion neutron source must In this study we have identified the most viable satisfy. In Section 3, we compare various types of toroidal fusion driver that can meet the needs of a toroidal fusion concepts for which there has been at materials production facility to be operational in the least some significant development work. -
Magnetic Fusion Technology 1St Edition Pdf Free Download
MAGNETIC FUSION TECHNOLOGY 1ST EDITION PDF, EPUB, EBOOK Thomas J Dolan | 9781447169277 | | | | | Magnetic Fusion Technology 1st edition PDF Book Design concept of LHD However, due to transit disruptions in some geographies, deliveries may be delayed. Connect with:. Magnetic confinement is one of two major branches of fusion energy research , along with inertial confinement fusion. GA's applied computer science programs are aimed at improving data acquisition, management, analysis, visualization, and collaboration for scientific research at large scales. Boundary physics Search WorldCat to find libraries that may hold this journal. Injecting frozen pellets of deuterium into the fuel mixture can cause enough turbulence to disrupt the islands. Mathematical models can determine the likelihood of a rogue wave and to calculate the exact angle of a counter-wave to cancel it out. Transport V. The next chapters deal with the principles, configuration, and application of high-beta stellarator, fast-linear-compression fusion systems, and ELMO Bumpy torus, as well as the magnetic confinement of high-temperature plasmas. Conclusions and perspectives Power exhaust 5. The mega amp spherical tokamak Equilibrium and Stability IV. This would require the pinch current to be reduced and the external stabilizing magnets to be made much stronger. Stellarators have seen renewed interest since the turn of the millennium as they avoid several problems subsequently found in the tokamak. Thermonuclear weapon Pure fusion weapon. Summary and conclusion Summary Part Four. First built in the UK in , and followed by a series of increasingly large and powerful machines in the UK and US, all early machines proved subject to powerful instabilities in the plasma. -
RESULTS from the ELMO BUMPY^TORUS in a THEORETICAL CONTEXT C. L. Hedrick, R. A. Dandl, R. A. Dory, H. 0. Eason, G. E. Guest, G. R
CORE Metadata, citation and similar papers at core.ac.uk Provided by UNT Digital Library RESULTS FROM THE ELMO BUMPY^TORUS IN A THEORETICAL CONTEXT C. L. Hedrick, R. A. Dandl, R. A. Dory, H. 0. Eason, G. E. Guest, G. R. Haste, H. Ikegami, E. F. Jaeger, N. H. Lazar, D. G. McAlees, D. H. McNeill, D. B. Nelson, L. W. Owen Oak Ridge National Laboratory, Oak Ridge, Tennessee USA Abstract: Theoretical and experimental results from the ELMO Bumpy Torus will be discussed with particular emphasis on macroscopic stability and transport. The ELMO Bumpy Torus (EBT) is a steady state device [1] composed of a linked set of twenty four 2-to-l mirrors, arranged to form a torus with plasma heated by microwave power. The plasma has two basic components; a mirror confined, high beta, hot electron plasma, forming hollow annuli between each pair of coils; and a moderate temperature toroidal plasma that threads each of the electron annuli. Experiments carried out dur- ing the past year have demonstrated the validity of the basic EBT premise: that plasma currents produced by the high-beta hot-electron annuli can provide macroscopically stable plasma confinement by creating average minimum-B. EBT has also exhibited confinement of particles and energy for 10's of milliseconds, high plasma purity, and no perceptible difficulties with field errors or convective cells. This paper summarizes the princi- pal experimental and theoretical features of the EBT research program. Stability Three distinct, reproducible modes of operation, the C-, T- and M-Modes are observed at successive lower ambient gas pressure. -
Where Are We Going? the Need for an Integrated View of In-Vessel Technology and the Path Forward Discussion
Where are we going? The need for an integrated view of in-vessel technology and the path forward Comment to FESAC Priorities Panel by RE Nygren, Sandia National Laboratories, 16august2012 Problem statement: Critical skill sets and the knowledge base needed to build in-vessel components for fusion are vanishing from the program due to retirements and redirected scope. Also vanishing in the physics-dominated program is a critical perspective from engineers and technologists about what is real and achievable in the future. The continuing wait for a significant expansion of R&D in materials (i.e., all of fusion nuclear technology) brings a very real threat of losing the experience base in the program needed for an informed well-led transition to a future stronger program in materials and technology. Recommendation: FES should develop and fund a limited set of R&D activities that engage a cadre of “experienced elders” to work with young researchers (future leaders) in two ways. 1. design and build in-vessel components - One idea is a US-supplied plasma facing component with refractory armor for an Asian tokamak. A less ambitious activity would be He-cooled refractory mockups for testing in a foreign facility. (US recently terminated this test capability.) Many countries have stated their interest in this type of activity. China, Japan, Korea, India have done so in discussions on bilateral exchanges. The EU and Russia already have an active program. 2. design studies on next device - Establish one or more design studies for the next machine(s) after ITER. Initially develop a self-consistent set of requirement for exhausting heat (may require an innovative divertor and new approach for protecting the first wall), heating and fueling the plasma, self-sufficient breeding of tritium, and systems for starting up, maintaining and shutting down the plasma. -
Nasa Tm X-73429 G
NASA TECHNICAL NASA TM X-73429 MEMORANDUM 0% C-." (NASA-TM-X-73429) ALTERNATIVE APPROACHES TO N76-23999 FUSION (-NASA) 54 p HC $4.50- CSCL 201 Unclas ____-____ __ G3/75 __28145 . ALTERNATIVE APPROACHES TO FUSION by J. Reece Roth Lewis Research Center Cleveland, Ohio 44135 Invited lecture for a course on controlled fusion sponsored by the IEEE Nuclear and Plasma Sciences Society Austin, Texas, May 26-28, 1976 CM ol r~° G %C0 VI.,> INTRODUCTION The scope of this lecture is restricted to magnetic confinement concepts which may provide back-up or second- generation alternatives for the Tokamak fusion reactor,-and which have been reduced to practice in the form of operating experimental apparatus. The Tokamak concept has been covered in previous lectures. 'The principal alternatives to Tokamak, theta pinches, open-ended geometries, and their modifications, will be covered in other lectures in this series. Inertial confinement schemes based on fusion microbombs which are ignited by irradiating fuel pellets with lasers or relativistic particle beams will also be covered in other lectures, as will the laser light pipe concept. The purpose of this lecture is to describe alternative plasma con finement schemes in such a way that the basic principles of each device can be understood and associated with its name, Desirable characteristics of an advanced fusion reactor will be presented, and the present Tokamak reactor conceptual designs will be examined in light of these criteria. Fusion reactions occur only at kinetic temperatures measured in tens of millions of degrees Kelvin. There are two recognized ways in which fusion reactions can be confined in the steady state, each employing a different field of force for confinement. -
Ca9110926 ALTERNATE FUSION CONCEPTS
///////// •'•7//.' Canadian Fusion Fuels Technology Project ca9110926 ALTERNATE FUSION CONCEPTS: STATUS AND PLANS CFFTP-G-9009 October 1990 P.J. Gierszewski, A.A. Harms* and S.B. Nickerson' ALTERNATE FUSION CONCEPTS: STATUS AND PLANS CFFTP-G-9009 October 1990 P.J. Gierszewski, A.A. Harms* and S.B. Nickerson' McMaster University Ontario Hydro Research Division CFFTP-G-9009 Prepared by: P.J. GierszewskiO Fusion Systems Engineer Fuel Systems & Materials Development Canadian Fusion Fuels Technology Project Reviewed by: Manager Fuel Systems & Materials Development Canadian Fusion Fuels Technology Project Approved by: D.P. Dautovich Program Manager Canadian Fusion Fuels Technology Project ACKNOWLEDGEMENTS We are grateful to the research groups at Los Alamos National Laboratory CTR Division (HDZP, CPRF, ZT-40, FRX-C, CTX), Spectra Technologies (LSX), Naval Research Laboratory (ZFX), University of Maryland (MS), Oak Ridge National Laboratory (ATF), Imperial College (HZP), Institut Gas lonizzati (RFX) and University of Stuttgart (DPF), who showed us their facilities, clarified the key issues, and discussed their results and program plans. We also particularly wish to thank D. Rej (LANL), A. Robson (NRL), R. Krakowski (LANL), P. Stangeby (UTIAS), J. Linhart (U. Pisa), M. Peng (ORNL) and G. Miley (U. Illinois) who kindly reviewed specific sections of the report. ALTERNATE FUSION CONCEPTS STATUS AND PLANS Table of Contents 1. Introduction 1 2. Advanced Tokamaks 3 3. Stellarator 11 4. Spherical Torus 18 5. Reversed-Field Pinch 24 6. Dense Z-Pinch 32 7. Field-Reversed Configuration 38 8. Spheromak 45 9. Ignition Experiments and Reactors 9.1 Ignition 52 9.2 Reactors 53 Appendix A: Other Concepts 62 A.1 Colliding Beam Fusion (Migma) 62 A.2 Electrostatic Confinement 63 A.3 Muon-Catalyzed Fusion 64 A.4 Spherical Pinch 64 A.5 Dense Plasma Focus 65 A.6 Linear Systems 66 A.7 Miscellaneous Concepts 67 Appendix B: Inertial Confinement 75 1. -
Compact Reversed-Field Pinch Reactors (CRFPR): Fusion-Power-Core Integration Study
LA-10500-MS LA— 10500-MS UC-20d DES6 001238 Issued: August 1985 Compact Reversed-Field Pinch Reactors (CRFPR): Fusion-Power-Core Integration Study C. Copenhaver R. A. Krakowski N. M. Schnurr R. L. Miller C. G. Bathke • R. L Hagenson* C. R. Mynard A. D. Chaffee C. Cappiello J.W.Davidson •Consultant at Los Alamos. Phillips Petroieun? Company, Bartlesville, OK 74004. Los Alamos National Laboratory Los Aîamos,New Mexico 87545 m: n OF THIS WBWR S ^L TABLE OF CONTENTS 1. INTRODUCTION 2 1.1. Background ..... ... 2 1.2. Scope 5 1.3. Fusion-Power-Core (FPC) Configuration and Standard Conditions . 6 2. FUSION-POWER-CORE MODELS 15 2.1. Two-Dimensional Neutronics 15 2.2. FPC Thermal-Hydraulics Model 22 2.2.1. First-Wall/Second-Wall Models 24 2.2.1.1. First-Wall Structural Analysis .... 26 2.2.1.2. First-Wall Thermal-Hydraulic Analysis 27 2.2.2. Limiter 31 2.2.3. Blanket 35 2.2.3.1. Blanket Hydraulic Analysis 35 2.2.3.2. Blanket Thermal Analysis 39 2.2.3.3. Channel Design 42 3. FUSION-POWER-CORE INTEGRATION 47 3.1. Power-Plant Energy Balance . « 47 3.2. Thermal-Hydraulic Design 49 3.2.1. Limiter Analysis 53 3.2.2. First-Wall/Second-Wall Analysis 54 3.2.3. Blanket Analysis 56 3.2.4. Shield Analysis 61 3.2.5. Design Summary ....... 62 3.3. Mechanical Design . 68 3.4. Base-Case Design Summary ... 72 3.5. Derated FPC Design Options id Tradeoffs 72 4. FPC MAINTENANCE APPROACH 81 4.1.