DOCSLIB.ORG

Space Plasma Physics

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text

Load more

About PPPL Established in 1951, the Princeton Plasma Physics Laboratory (PPPL) is dedicated to de- veloping the scientifi c and technological knowledge base for fusion energy as a safe, econom- ical, and environmentally attractive energy source for the world’s long-term energy require- ments. It was the site of the Tokamak Fusion Test Reactor which completed a historic series of experiments using deuterium-tritium fuel in April 1997. A new innovative facility, the National Spherical Torus Experiment, came into operation in 1999, ahead of schedule and on budget. Princeton University manages PPPL under contract with the U.S. Department of Energy. The fi scal year 2003 budget was approximately $66.5 million. The number of full-time reg- ular employees at the end of the fi scal year was 420, not including approximately 30 subcon- tractors and limited duration employees, 35 graduate students, and visiting research staff. The Laboratory is sited on 88 acres of Princeton University’s James Forrestal Campus, about four miles from the main campus. Through its efforts to build and operate magnetic fusion devices, PPPL has gained exten- sive capabilities in a host of disciplines including advanced computational simulations, vacuum technology, mechanics, materials science, electronics, computer technology, and high-voltage power systems. In addition, PPPL scientists and engineers are applying knowledge gained in fusion research to other theoretical and experimental areas including the development of plas- ma thrusters and propagation of intense beams of ions. The Laboratory’s Offi ce of Technolo- gy Transfer assists industry, other universities, and state and local government in transferring these technologies to the commercial sector. The Laboratory’s graduate education and science education programs provide educational opportunities for students and teachers from elementary school through postgraduate studies. On The Cover A new experimental device, the National Compact Stellarator Experiment (NCSX), is be- ing constructed at the Princeton Plasma Physics Laboratory in partnership with the Oak Ridge National Laboratory. NCSX is the centerpiece of a national program to develop the compact- stellarator plasma-confi nement concept. During fi scal year 2003, the NCSX fabrication proj- ect offi cially started. Good progress on its design permitted the project to advance from con- ceptual design to a level of maturity suffi cient to establish the cost and schedule baseline for project execution. A computer-generated cutaway rendition of NCSX is shown with individual key compo- nents. From the upper left are: one fi eld-period subassembly, a modular coil subassembly, a to- roidal-fi eld coil subassembly, the modular coil assembly, an NCSX plasma and the modular coils, and the NCSX vacuum vessel assembly with thermal insulation. This publication highlights activities at the Princeton Plasma Physics Laboratory for fi scal year 2003 — 1 October 2002 through 30 September 2003. Mission The U.S. Department of Energy’s Princeton Plasma Physics Laboratory is a Collaborative National Center for plasma and fusion science. Its primary mission is to develop the scientifi c understanding and the key innovations which will lead to an attractive energy source. Associated missions include conducting world-class research along the broad frontier of plasma science and technology, and providing the highest quality of scientifi c education. Vision Deepening the understanding of plasmas and creating key innovations to make fusion power a practical reality. i ii Advantages of Fusion Energy • Worldwide availability of inexhaustible low-cost fuel. • No chemical combustion products and therefore no contribution to acid rain or global warming. • No runaway reaction possible. • Materials and by-products unsuitable for weapons production. • Radiological hazards thousands of times less than from fi ssion. iii iv Table of Contents From the Director ....................................................................................vii Research National Spherical Torus Experiment ...................................................1 Current Drive Experiment-Upgrade ...................................................15 Magnetic Reconnection Experiment ...................................................23 Theory and Advanced Simulations .....................................................31 Computational Plasma Physics ............................................................47 Off-site Research ................................................................................57 Doublet-III-D Collaborations ......................................................57 Alcator C-Mod Collaborations .....................................................61 International Collaborations .........................................................67 Space Plasma Physics ..........................................................................73 Basic and Applied Physics Experiments ..............................................81 Hall Thruster Experiment ............................................................81 Magnetic Nozzle Experiment .......................................................83 FRC/RMF Experiment ................................................................85 Nonneutral Plasmas and High-intensity Accelerators ...................86 Diagnostic Development ...............................................................91 Liquid Metal Experiment .............................................................94 Advanced Fusion Devices and Studies National Compact Stellarator Experiment ..........................................97 Fusion Ignition Research Experiment ...............................................105 Engineering and Technical Infrastructure .............................................113 Environment, Safety, and Health ...........................................................125 Applied Research and Technology Transfer ...........................................127 Patents and Invention Disclosures .........................................................137 Education Graduate Education .........................................................................139 Science Education ............................................................................143 Awards and Honors ...............................................................................149 The Year in Pictures ...............................................................................153 Financial Summary ................................................................................157 Organization and Staffi ng .....................................................................159 PPPL Advisory Council .........................................................................161 Publications ...........................................................................................163 Abbreviations, Acronyms, and Symbols ................................................201 v vi From the Director n January 30, 2003, President Bush announced “that the Unit- Oed States will join ITER, an am- bitious international research project to harness the promise of fusion energy. The results of ITER will advance the effort to produce clean, safe, renewable, and com- mercially available fusion energy by the middle of this century. Commercialization of fusion has the potential to dramatical- ly improve America’s energy security while signifi cantly reducing air pollution and emissions of greenhouse gases.” Robert J. Goldston On the same day, Secretary of Ener- gy Spencer Abraham visited the Princeton perimental results from PPPL collaboration Plasma Physics Laboratory (PPPL) and at the W7-AS stellarator in Germany con- stated, “By the time our young children tinue to indicate that this will be a very ex- reach middle age, fusion may begin to de- citing experiment. The remarkable steadi- liver energy independence… and energy ness of stellarator plasmas in W7-AS, even abundance… to all nations rich and poor. at high beta, is very impressive. Fusion is a promise for the future we must Despite loss of eight experimental run- not ignore. But let me be clear, our decision weeks on the National Spherical Torus to join ITER in no way means a lesser role Experiment (NSTX), due to a coil joint for the fusion programs we undertake here failure, very good progress was made on at home. It is imperative that we maintain bringing new capabilities on line, includ- and enhance our strong domestic research ing an extremely high-resolution instru- program — at Princeton, at the universi- ment for measuring plasma ion temper- ties and at our other labs. Critical science ature and toroidal rotation, which will needs to be done in the U.S., in parallel allow unprecedented detail in determining with ITER, to strengthen our competitive the effects of magnetic structures on ro- position in fusion technology.” tating plasmas — and vice versa. Thermal With this degree of support at the high- confi nement and fast-ion data also pro- est levels in the Administration, FY03 was vided new insight into the physics of the a heady year for fusion research. At PPPL spherical torus confi guration. The NSTX we continued to make important advanc- underwent a very successful fi ve-year plan es in both the experimental and theoretical review, outlining the NSTX scientifi c pro- research needed to create the future envi- gram, including both research goals and sioned by our leaders. new facility capabilities that are needed to The National Compact
Recommended publications
  • Fusion-The-Energy-Of-The-Universe

    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.
  • The US and the International Quest for Fusion Energy

    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.
  • STATUS of FUSION RESEARCH and IMPLICATIONS for D-3He SYSTEMS

    STATUS of FUSION RESEARCH and IMPLICATIONS for D-3He SYSTEMS

    STATUS OF FUSION RESEARCH AND IMPLICATIONS FOR D-3He SYSTEMS George H. Miley Fusion Studies Laboratory University of Illinois 103 South Goodwin Avenue Urbana, IL 61801 World-wide programs in both magnetic confinement and inertial confinement fusion research have made steady progress towards the experimental demonstration of energy breakeven.(*-') Both approaches are now in reach of this goal within the next few years using a D-T equivalent plasma. For magnetic confinement, this step is expected in one of the large tokamak experimental devices such as TFTR (USA), JET (EC), JT-60 (Japan), or T-15 (USSR). Upgraded versions of the Nova glass laser (USA) and CEKKO (Japan) also appear to have a good chance at this goal. The light-ion beam facility "PBFA-11" is viewed as a "dark horse" candidate. Recent physics parameters obtained in these various experiments will be briefly reviewed in this presentation. However, after breakeven is achieved, considerable time and effort must still be expended to develop a usable power plant. The time schedules envisioned by workers in the various countries involved are fairly similar.(l-J) For example, the European Community (EC) proposes to go from the physics studies in JET to an engineering test reactor (NET) which has a construction decision in 1991. This is projected to result in a demonstration reactor after 2015. Plans for inertial confinement are-currently centered on the development of a "next-step'' target facility based on an advanced 5-megajoule laser on roughly the same time scale as NET.(5) The facilities required for both magnetic and inertial confinement will be large and expensive.
  • The Fairy Tale of Nuclear Fusion L

    The Fairy Tale of Nuclear Fusion L

    The Fairy Tale of Nuclear Fusion L. J. Reinders The Fairy Tale of Nuclear Fusion 123 L. J. Reinders Panningen, The Netherlands ISBN 978-3-030-64343-0 ISBN 978-3-030-64344-7 (eBook) https://doi.org/10.1007/978-3-030-64344-7 © The Editor(s) (if applicable) and The Author(s), under exclusive license to Springer Nature Switzerland AG 2021 This work is subject to copyright. All rights are solely and exclusively licensed by the Publisher, whether the whole or part of the material is concerned, specifically the rights of translation, reprinting, reuse of illustrations, recitation, broadcasting, reproduction on microfilms or in any other physical way, and transmission or information storage and retrieval, electronic adaptation, computer software, or by similar or dissimilar methodology now known or hereafter developed. The use of general descriptive names, registered names, trademarks, service marks, etc. in this publication does not imply, even in the absence of a specific statement, that such names are exempt from the relevant protective laws and regulations and therefore free for general use. The publisher, the authors and the editors are safe to assume that the advice and information in this book are believed to be true and accurate at the date of publication. Neither the publisher nor the authors or the editors give a warranty, expressed or implied, with respect to the material contained herein or for any errors or omissions that may have been made. The publisher remains neutral with regard to jurisdictional claims in published maps and institutional affiliations. This Springer imprint is published by the registered company Springer Nature Switzerland AG The registered company address is: Gewerbestrasse 11, 6330 Cham, Switzerland When you are studying any matter or considering any philosophy, ask yourself only what are the facts and what is the truth that the facts bear out.
  • Princeton University Plasma Physics Laboratoi - Princeton, New Jersey 0L343

    Princeton University Plasma Physics Laboratoi - Princeton, New Jersey 0L343

    Annual Report Covering the Period October 1. 1985 to September 30, 1386 Princeton University Plasma Physics Laboratoi - Princeton, New Jersey 0L343 PPPL-Q-44 PPPL-Q—44 DE88 007501 Edited by Carol A. Phillips DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United Stales Government. Neither the United Slates Governmeni 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 iti use would not infringe privately owned rights. Rrfsr ence herein to any specific commercial pruduct, process, or scmce by trade name, trademark, manufacturer, or otherwise docs not necessarily constitute or imply its endorsement, recom­ mendation, or Favoring by the United Stales Government or any agency thereof The views and opinions of authors expressed herein do not necessarily state or reflect those of the United Slates Government or any agency thereof. Unless otherwise designated, the work in this report is funded by the United States Depart­ ment of Energy under Contract DE-AC02-76- CHO-3073. Printed in the United States of America ^ Or Tiny pntfjm^T 1J: -^ Contents Preface 1 Principal Parameters Achieved in Experimental Devices 3 Tokamak Fusion Test Reactor 5 Princeton Large Torus 38 Princeton Beta Experiment 48 S-1 Spheromak 58 Current-Drive Experiment 64 X-Ray Laser Studies 67 Theoretical Division 74 Tokamak
  • Selection of a Toroidal Fusion Reactor Concept for a Magnetic Fusion Production Reactor 1

    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.
  • December 1995

    December 1995

    DOEIEA-1108 ENVIRONMENTAL ASSESSMENT THE NATIONAL SPHERICAL TOKAMAK EXPERIMENT AT THE PRINCETON PLASMA PHYSICS LABORATORY December 1995 DECLAIMER This report was prepared as an account of work sponsored by an agency of 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. U.S. DEPARTMENT OF ENERGY ARGONNE, ILLINOIS 60439 THE NATIONAL SPHERICAL TOKAMAK EXPERIMENT AT THE PRINCETON PLASMA PHYSICS LABORATORY 1.0 PURPOSE AND NEED FOR THE PROPOSED ACTION If the United States is to meet the energy needs of the future, it is essential that new technologies emerge to compensate for dwindling supplies of fossil fuels and the eventual depletion of fissionable uranium used in present-day nuclear reactors. Fusion energy has the potential to become a major source of energy for the future. Power from fusion would provide a substantially reduced environmental impact as compared with other forms of energy generation. The purpose of the National Spherical Tokamak Experiment (NSTX) is to support fusion physics development and technology, by providing an experimental device to investigate the confinement and performance of plasmas produced in a spherical shaped tokamak.
  • Lawrence Berkeley Laboratory UNIVERSITY of CALIFORNIA F

    Lawrence Berkeley Laboratory UNIVERSITY of CALIFORNIA F

    LBL-1l146 C ...,r Lawrence Berkeley Laboratory UNIVERSITY OF CALIFORNIA f ......-' Accelerator & Fusion Research Division Presented at the Xlth International Conference on High Energy Accelerators, Geneva, Switzerland, July 7-11, 1980 HEAVY ION INERTIAL FUSION ;!~ ;'~; v~' f~ ~ I'J CE LEY 1.J..\.BORAIOJrY D. Keefe and A.M. Sessler JAN b 1981 July 1980 ....., .... ;-~ PI, [;2 Y .l\}"') ',:1.: 'SNTS SEC,: ,; \, \ TWO-WEEK LOAN COpy This is a Library Circulating Copy which may be borrowed for two weeks. .­ For a personal retention copy, call Tech. Info. Division, Ext. 6782. r V> r \ Prepared for the U.S. Department of Energy under Contract W-7405-ENG-48 HEAVY ION INERTIAL FUSION*) D. Keefe and A.M. Sessler Lawrence Berkeley Laboratory, University of California, Berkeley, CA 94720 ABSTRACT Inertial fusion has not yet been as well explored as magnetic fusion but can offer certain advantages as an alternative source of electric energy for the future. Present experiments use high-power beams from lasers and light-ion diodes to compress the deuterium-tritium (D-T) pellets but these will probably be unsuitable for a power plant. A more promising method is to use intense heavy-ion beams from accelerator systems similar to those used for nuclear and high-energy physics; the present paper addresses itself to this alternative. As will be demonstrated the very high beam power needed poses new design questions, from the ion source through the accelerating system, the beam transport system, to the final focus. These problems will require extensive study, both theoretically and experimentally, over the next several years before an optimum design for an inertial fusion driver can be arrived at.
  • Formation of a 100-Ka Tokamak Discharge in the Princeton Large Torus by Lower Hybrid Waves

    Formation of a 100-Ka Tokamak Discharge in the Princeton Large Torus by Lower Hybrid Waves

    VOLUME 52, NUMBER 12 PHYSICAL REVIEW LETTERS 19 MARCH 1984 Formation of a 100-kA Tokamak Discharge in the Princeton Large Torus by Lower Hybrid Waves F. Jobes, J. Stevens, R. Bell, S. Bernabei, A. Cavallo, T. K. Chu, S. Cohen, B. Denne, P. Efthimion, E. Hinnov, W. Hooke, J. Hosea, E. Mazzucato, R. McWilliams, R. Motley, S. Suckewer, G. Taylor, J. Timberlake, S. von Goeler, and R. Wilson Princeton Plasma Physics Laboratory, Princeton University, Princeton, 1Vew Jersey 08544 (Received 19 December 1983) The development of noninductive current drive is of great importance in establishing the tokamak as a long-pulse or steady-state fusion reactor. Lower hybrid waves, carrying 200 kW of power at 800 MHz, have been launched into the Princeton Large Torus tokamak to ini- tiate and drive the discharge current to a level in excess of 100 kA. PACS numbers: 52.55.Gb, 52.80.-s Up to the present time tokamak devices have the lower hybrid waves alone or by electron cyclo- been inherently pulsed, because they rely on a tron resonance. ' " In this Letter we report suc- transformer to drive the plasma current. This cessful efforts to create a target plasma and to raise current, in interaction with a transverse magnetic the plasma current to 100 kA by lower hybrid field, provides the restoring force needed to hold waves, unassisted by induction from the primary the plasma column in equilibrium away from the transformer or by the application of power at the vacuum walls. Prospects for the tokamak as a electron cyclotron frequency. fusion reactor would be greatly enhanced by the The experiment was carried out in the PLT development of a reliable method of steady-state tokamak, ' a torus with minor radius 0.4 m and ma- current drive.

  • Fusion As a Research Program

    Chapter 6 Fusion as a Research Program . Page Near-Term Benefits. + . , .............131 Development of Plasma Physics . ...+..... ...........131 Educating Plasma Physicists . .....+... .......................132 Advancing Science and Technology . ........132 Stature ● **..****.*.***** . ***.************ .. *******~*****.. ......133 Near-Term Benefits. ........= ...134 Magnetic Fusion Funding . ..........................134 Magnetic Fusion Personnel. .... ............139 Participation in Magnetic Fusion Research.. .. ... + ......140 ‘Department of Energy National Laboratories . m +.. 140 Universities and Colleges . + .+....... .......143 Private Industry . .S. ... ... .O. ....O . ........0.0...0.147 summary and Conclusions. ... .+ ......151 Figures Figure No. Page 6-1. Federal Funding of Plasma Physics in 1984. ., ........132 62. Defense and Civilian Federal R&D Expenditures . ....................134 6-3. Major Components in Federally Funded R&O in Fiscal Year 1987. ......135 64. Historical Component Funding Levels of Federal R&D Programs... .. ....136 6-6 MajorDOE Civilian R&D Funding at National Laboratories in Fiscal Year1987 .**.+** ● . ● ****4** ● ***.... .*.**B** .***.*.. 141 Page *....*. ● ✎☞☛✎✎✎✎ 137 .*+**.** ● .*.*.. 139 .****** .***.... 141 .*+**.. 145 ,...., ● *,*... ● o 147 Chapter 6 Fusion as a Research Program The ultimate objective of fusion research is to A complete analysis of the fusion energy program produce a commercially viable energy source. must include the immediate, indirect benefits and Yet, because the research program is exploring costs of the ongoing research effort, in addition new realms of science and technology, it also pro- to its progress in reaching its long-term goal. vides a weal h of near-term, non-energy benefits. NEAR-TERM BENEFITS Fusion research has provided four major near- and fluid dynamics. Today, plasma physics goes term, non-energy benefits. It has been a driving beyond fusion research. Since most known mat- force behind the development of plasma physics.
  • Princeton University Plasma Physics Laboratory Princeton, New Jersey

    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
  • PROGRESS REPORT on CONTROLLED FUSION

    PROGRESS REPORT on CONTROLLED FUSION

    PROGRESS REPORT on CONTROLLED FUSION RESEARCH* by M. H. BRENNAN October, 1972 School of Physical Sciences The Flinders University of South Australia Bedford Park, South Australia 5042 'rReport prepared for the Australian Atomic Energy Commission. 1. INTRODUCTION In this report a survey is made of the international research programme directed towards the development of a controlled thermonuclear fusion reactor. The report is based on observations made during an overseas trip which included attendance at a meeting of the international Fusion Research Council and the Fifth European Conference on Controlled Fusion and Plasma Physics. The itinerary for the trip, which was from 13th August to 28th September, 1972, is included as Appendix A to this report. In order to provide a basis for evaluating the fusion research programme a brief summary is given in Section 2 of the basic requirements for a fusion reactor. In Sections 3 and k of the report brief summeries are given of the main features of the Council meeting and the Fifth European Conference. The current state of fusion research is reviewed in Section 5° The final Section of the report includes a discussion of the present and near-future international fusion research programme, and some comments on the Australian programme. 2. THE FUSION REACTOR 2.1 The Scientific Problem The most favourable nuclear reaction for the release of nuclear energy from the fusion of light elements is the deuterium-tritium reaction (D-T reaction). This reaction has a cross section, at energies of -100 keV, of several hundred times that for the D-D reaction (deuterium-deuterium).