The Helias Reactor
Total Page:16
File Type:pdf, Size:1020Kb
Load more
Recommended publications
-
Richard G. Hewlett and Jack M. Holl. Atoms
ATOMS PEACE WAR Eisenhower and the Atomic Energy Commission Richard G. Hewlett and lack M. Roll With a Foreword by Richard S. Kirkendall and an Essay on Sources by Roger M. Anders University of California Press Berkeley Los Angeles London Published 1989 by the University of California Press Berkeley and Los Angeles, California University of California Press, Ltd. London, England Prepared by the Atomic Energy Commission; work made for hire. Library of Congress Cataloging-in-Publication Data Hewlett, Richard G. Atoms for peace and war, 1953-1961. (California studies in the history of science) Bibliography: p. Includes index. 1. Nuclear energy—United States—History. 2. U.S. Atomic Energy Commission—History. 3. Eisenhower, Dwight D. (Dwight David), 1890-1969. 4. United States—Politics and government-1953-1961. I. Holl, Jack M. II. Title. III. Series. QC792. 7. H48 1989 333.79'24'0973 88-29578 ISBN 0-520-06018-0 (alk. paper) Printed in the United States of America 1 2 3 4 5 6 7 8 9 CONTENTS List of Illustrations vii List of Figures and Tables ix Foreword by Richard S. Kirkendall xi Preface xix Acknowledgements xxvii 1. A Secret Mission 1 2. The Eisenhower Imprint 17 3. The President and the Bomb 34 4. The Oppenheimer Case 73 5. The Political Arena 113 6. Nuclear Weapons: A New Reality 144 7. Nuclear Power for the Marketplace 183 8. Atoms for Peace: Building American Policy 209 9. Pursuit of the Peaceful Atom 238 10. The Seeds of Anxiety 271 11. Safeguards, EURATOM, and the International Agency 305 12. -
Inis: Terminology Charts
IAEA-INIS-13A(Rev.0) XA0400071 INIS: TERMINOLOGY CHARTS agree INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, AUGUST 1970 INISs TERMINOLOGY CHARTS TABLE OF CONTENTS FOREWORD ... ......... *.* 1 PREFACE 2 INTRODUCTION ... .... *a ... oo 3 LIST OF SUBJECT FIELDS REPRESENTED BY THE CHARTS ........ 5 GENERAL DESCRIPTOR INDEX ................ 9*999.9o.ooo .... 7 FOREWORD This document is one in a series of publications known as the INIS Reference Series. It is to be used in conjunction with the indexing manual 1) and the thesaurus 2) for the preparation of INIS input by national and regional centrea. The thesaurus and terminology charts in their first edition (Rev.0) were produced as the result of an agreement between the International Atomic Energy Agency (IAEA) and the European Atomic Energy Community (Euratom). Except for minor changesq the terminology and the interrela- tionships btween rms are those of the December 1969 edition of the Euratom Thesaurus 3) In all matters of subject indexing and ontrol, the IAEA followed the recommendations of Euratom for these charts. Credit and responsibility for the present version of these charts must go to Euratom. Suggestions for improvement from all interested parties. particularly those that are contributing to or utilizing the INIS magnetic-tape services are welcomed. These should be addressed to: The Thesaurus Speoialist/INIS Section Division of Scientific and Tohnioal Information International Atomic Energy Agency P.O. Box 590 A-1011 Vienna, Austria International Atomic Energy Agency Division of Sientific and Technical Information INIS Section June 1970 1) IAEA-INIS-12 (INIS: Manual for Indexing) 2) IAEA-INIS-13 (INIS: Thesaurus) 3) EURATOM Thesaurusq, Euratom Nuclear Documentation System. -
The Stellarator Program J. L, Johnson, Plasma Physics Laboratory, Princeton University, Princeton, New Jersey
The Stellarator Program J. L, Johnson, Plasma Physics Laboratory, Princeton University, Princeton, New Jersey, U.S.A. (On loan from Westlnghouse Research and Development Center) G. Grieger, Max Planck Institut fur Plasmaphyslk, Garching bel Mun<:hen, West Germany D. J. Lees, U.K.A.E.A. Culham Laboratory, Abingdon, Oxfordshire, England M. S. Rablnovich, P. N. Lebedev Physics Institute, U.S.3.R. Academy of Sciences, Moscow, U.S.S.R. J. L. Shohet, Torsatron-Stellarator Laboratory, University of Wisconsin, Madison, Wisconsin, U.S.A. and X. Uo, Plasma Physics Laboratory Kyoto University, Gokasho, Uj', Japan Abstract The woHlwide development of stellnrator research is reviewed briefly and informally. I OISCLAIWCH _— . vi'Tli^liW r.'r -?- A stellarator is a closed steady-state toroidal device for cer.flning a hot plasma In a magnetic field where the rotational transform Is produced externally, from torsion or colls outside the plasma. This concept was one of the first approaches proposed for obtaining a controlled thsrtnonuclear device. It was suggested and developed at Princeton in the 1950*s. Worldwide efforts were undertaken in the 1960's. The United States stellarator commitment became very small In the 19/0's, but recent progress, especially at Carchlng ;ind Kyoto, loeethar with «ome new insights for attacking hotii theoretics] Issues and engineering concerns have led to a renewed optimism and interest a:; we enter the lQRO's. The stellarator concept was borr In 1951. Legend has it that Lyman Spiczer, Professor of Astronomy at Princeton, read reports of a successful demonstration of controlled thermonuclear fusion by R. -
Fusion & High Energy Density Plasma Science
Fusion & High Energy Density Plasma Science Opportunities using Pulsed Power Daniel Sinars, Sandia National Laboratories Fusion Power Associates Dec. 4-5, 2018 Sandia National Laboratories is a multimission laboratory managed and operated by National Technology and Engineering Solutions of Sandia, LLC., a wholly owned subsidiary of Honeywell International, Inc., for the U.S. Department of Energy’s National Nuclear Security Administration under contract DE-NA-0003525. Sandia is the home of Z, the world’s largest pulsed power facility, and its adjacent multi-kJ Z-Beamlet and Z-PW lasers Pulsed power development area Z Periscope ZBL/ZPW Chama ZPW ZBL Chamber Jemez Chamber Chaco Pecos Target Chamber Chaco Chaco Probe Chambers Laser Beam Using two HED facilities, we have demonstrated the scaling of magneto-inertial fusion over factors of 1000x in energy 3 Our fusion yields have been increasing as expected with increased fuel preheating and magnetization Progress since 1st MagLIF in 2014 Demonstrated platform on Omega • Improved laser energy coupling • Improved magnetic field from ~0.3 kJ to 1.4 kJ strength from 9 T to 27 T • Demonstrated 6x improvement • Achieved record MIF yields on in fusion performance, reaching Omega of 5x109 DD in 2018 2.5 kJ DT-equivalent in 2018 4 We believe that Z is capable of producing a fusion yield of ~100 kJ DT-equivalent with MagLIF, though doing it with DT would exceed our safety thresholds for both T inventory & yield Preheat Energy = 6 kJ into 1.87 mg/cc DT § 2D simulations indicate a 22+ MA and 25+ T with 22.6 MA 6 kJ of preheat could produce ~100 kJ 21.1 MA § Presently, we cannot produce these inputs 17.4 MA S. -
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). -
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. -
Highlights in Early Stellarator Research at Princeton
J. Plasma Fusion Res. SERIES, Vol.1 (1998) 3-8 Highlights in Early Stellarator Research at Princeton STIX Thomas H. Department of Astrophysical Sciences, Princeton University, Princeton, NJ 08540, USA (Received: 30 September 1997/Accepted: 22 October 1997) Abstract This paper presents an overview of the work on Stellarators in Princeton during the first fifteen years. Particular emphasis is given to the pioneering contributions of the late Lyman Spitzer, Jr. The concepts discussed will include equilibrium, stability, ohmic and radiofrequency plasma heating, plasma purity, and the problems associated with creating a full-scale fusion power plant. Brief descriptions are given of the early Princeton Stellarators: Model A, Model B, Model B-2, Model B-3, Models 8-64 and 8-65, and Model C, and also of the postulated fusion power plant, Model D. Keywords: Spitzer, Kruskal, stellarator, rotational transform, Bohm diffusion, ohmic heating, magnetic pumping, ion cyclotron resonance heating (ICRH), magnetic island, tokamak On March 31 of this year, at the age of 82, Lyman stellarator was brought to the headquarters of the U.S. Spitzer, Jr., a true pioneer in the fields of astrophysics Atomic Energy Commission in Washington where it re- and plasma physics, died. I wish to dedicate this presen- ceived a favorable reception. Spitzer chose the name tation to his memory. "Project Matterhorn" for the project which was to be Forty-six years ago, in early 1951, Spitzer, then sited in the Princeton area, on the newly acquired For- chair of the Department of Astronomy at Princeton restal tract, and funding began on July 1 of that year University, together with Princeton physicist John 121- Wheeler, had been thinking about the physics of ther- Spitzer's earliest stellarator papers comprise a truly monoclear processes. -
Tomographic Inversion of Wendelstein 7-X Stellarator Plasmas
45th EPS Conference on Plasma Physics P4.1056 Tomographic inversion of Wendelstein 7-X stellarator plasmas C. Brandt1, H. Thomsen1, T. Andreeva, N. Lauf1, U. Neuner1, K. Rahbarnia1, J. Schilling1, T. Broszat1, R. Laube1 and the Wendelstein 7-X Team 1 Max-Planck-Institute for Plasma Physics, Greifswald, Germany In the operational phase OP1.2a (Aug-Dec 2017) of the Wendelstein 7-X (W7-X) stellarator experiment the soft X-ray tomography diagnostic (XMCTS: soft X-ray multi camera tomogra- phy system) has been commissioned. Soft X-ray tomography systems are powerful diagnostics for high temperature plasmas measuring spatiotemporal X-ray emissivity profiles. The XMCTS consists of 20 poloidally arranged pinhole cameras at one toroidal location observing a triangu- lar shaped up-down symmetric plasma cross section. X-ray radiation is mainly emitted in the hot plasma core (electron temperatures > 1keV). In the pinhole cameras the plasma radiation is filtered by a beryllium foil of 12:5 mm thickness being transmissible for X-ray radiation above 1keV. Taking into account the detector silicon thickness of 100 mm the detectable energy range is limited to approximately 1 − 10keV. With 18 available cameras in OP1.2a the soft X-ray emissivity has been recorded along 324 lines-of-sight with a time resolution of 0:5 ms. The presentation concentrates on the preparation and first results of the tomographic inver- sion. For correct calculation of the tomograms, both, the knowledge of the exact geometry of the lines-of-sight and the sensitivity of each photodiode are of crucial importance. The as-built coordinates of the cameras have been measured after the in-vessel installation. -
On Fusion Driven Systems (FDS) for Transmutation
R-08-126 On fusion driven systems (FDS) for transmutation O Ågren Uppsala University, Ångström laboratory, division of electricity V E Moiseenko Institute of Plasma Physics, National Science Center Kharkov Institute of Physics and Technology K Noack Forschungszentrum Dresden-Rossendorf October 2008 Svensk Kärnbränslehantering AB Swedish Nuclear Fuel and Waste Management Co Box 250, SE-101 24 Stockholm Tel +46 8 459 84 00 CM Gruppen AB, Bromma, 2008 ISSN 1402-3091 Tänd ett lager: SKB Rapport R-08-126 P, R eller TR. On fusion driven systems (FDS) for transmutation O Ågren Uppsala University, Ångström laboratory, division of electricity V E Moiseenko Institute of Plasma Physics, National Science Center Kharkov Institute of Physics and Technology K Noack Forschungszentrum Dresden-Rossendorf October 2008 This report concerns a study which was conducted for SKB. The conclusions and viewpoints presented in the report are those of the authors and do not necessarily coincide with those of the client. A pdf version of this document can be downloaded from www.skb.se. Summary This SKB report gives a brief description of ongoing activities on fusion driven systems (FDS) for transmutation of the long-lived radioactive isotopes in the spent nuclear waste from fission reactors. Driven subcritical systems appears to be the only option for efficient minor actinide burning. Driven systems offer a possibility to increase reactor safety margins. A comparatively simple fusion device could be sufficient for a fusion-fission machine, and transmutation may become the first industrial application of fusion. Some alternative schemes to create strong fusion neutron fluxes are presented. 3 Sammanfattning Denna rapport för SKB ger en övergripande beskrivning av pågående aktiviteter kring fusionsdrivna system (FDS) för transmutation av långlivade radioaktiva isotoper i kärnavfallet från fissionskraftverk. -
Fusion Public Meeting Slides-03302021-FINAL
TitleDeveloping Lorem a Regulatory Ipsum Framework for Fusion Energy Systems March 30, 2021 Agenda Time Topic Speaker(s) 12:30-12:40pm Introduction/Opening Remarks NRC Discussion on NAS Report “Key Goals and Innovations Needed for a U.S. Fusion Jennifer Uhle (NEI) 12:40-1:10pm Pilot Plant” Rich Hawryluk (PPPL) Social License and Ethical Review of Fusion: Methods to Achieve Social Seth Hoedl (PRF) 1:10-1:40pm Acceptance Developers Perspectives on Potential Hazards, Consequences, and Regulatory Frameworks for Commercial Deployment: • Fusion Industry Association - Industry Remarks Andrew Holland (FIA) 1:40-2:40pm • TAE – Regulatory Insights Michl Binderbauer (TAE) • Commonwealth Fusion Systems – Fusion Technology and Radiological Bob Mumgaard (CFS) Hazards 2:40-2:50pm Break 2:50-3:10pm Licensing and Regulating Byproduct Materials by the NRC and Agreement States NRC Discussions of Possible Frameworks for Licensing/Regulating Commercial Fusion • NRC Perspectives – Byproduct Approach NRC/OAS 3:10-4:10pm • NRC Perspectives – Hybrid Approach NRC • Industry Perspectives - Hybrid Approach Sachin Desai (Hogan Lovells) 4:10-4:30pm Next Steps/Questions All Public Meeting Format The Commission recently revised its policy statement on how the agency conducts public meetings (ADAMS No.: ML21050A046). NRC Public Website - Fusion https://www.nrc.gov/reactors/new-reactors/advanced/fusion-energy.html NAS Report “Key Goals and Innovations Needed for a U.S. Fusion Pilot Plant” Bringing Fusion to the U.S. Grid R. J. Hawryluk J. Uhle D. Roop D. Whyte March 30, 2021 Committee Composition Richard J. Brenda L. Garcia-Diaz Gerald L. Kathryn A. Per F. Peterson (NAE) Jeffrey P. Hawryluk (Chair) Savannah River National Kulcinski (NAE) McCarthy (NAE) University of California, Quintenz Princeton Plasma Laboratory University of Oak Ridge National Berkeley/ Kairos Power TechSource, Inc. -
Stellarator and Tokamak Plasmas: a Comparison
Home Search Collections Journals About Contact us My IOPscience Stellarator and tokamak plasmas: a comparison This article has been downloaded from IOPscience. Please scroll down to see the full text article. 2012 Plasma Phys. Control. Fusion 54 124009 (http://iopscience.iop.org/0741-3335/54/12/124009) View the table of contents for this issue, or go to the journal homepage for more Download details: IP Address: 130.183.100.97 The article was downloaded on 22/11/2012 at 08:08 Please note that terms and conditions apply. IOP PUBLISHING PLASMA PHYSICS AND CONTROLLED FUSION Plasma Phys. Control. Fusion 54 (2012) 124009 (12pp) doi:10.1088/0741-3335/54/12/124009 Stellarator and tokamak plasmas: a comparison P Helander, C D Beidler, T M Bird, M Drevlak, Y Feng, R Hatzky, F Jenko, R Kleiber,JHEProll, Yu Turkin and P Xanthopoulos Max-Planck-Institut fur¨ Plasmaphysik, Greifswald and Garching, Germany Received 22 June 2012, in final form 30 August 2012 Published 21 November 2012 Online at stacks.iop.org/PPCF/54/124009 Abstract An overview is given of physics differences between stellarators and tokamaks, including magnetohydrodynamic equilibrium, stability, fast-ion physics, plasma rotation, neoclassical and turbulent transport and edge physics. Regarding microinstabilities, it is shown that the ordinary, collisionless trapped-electron mode is stable in large parts of parameter space in stellarators that have been designed so that the parallel adiabatic invariant decreases with radius. Also, the first global, electromagnetic, gyrokinetic stability calculations performed for Wendelstein 7-X suggest that kinetic ballooning modes are more stable than in a typical tokamak. -
The High-Field Path to Practical Fusion Energy
The High-Field Path to Practical Fusion Energy M. Greenwald, D. Whyte, P. Bonoli, D. Brunner, Z. Hartwig, J. Irby, B. LaBombard, E. Marmar, J. Minervini, R. Mumgaard, B. Sorbom, M. Takayasu, J. Terry, R. Vieira, S. Wukitch MIT – Plasma Science & Fusion Center Objective This white paper outlines a vision and describes a coherent roadmap to achieve practical fusion energy in less time and at less expense than the current pathway. The key technologies that enable this path are high-field, high-temperature demountable superconducting magnets, a molten salt liquid blanket, high-field-side lower hybrid current drive and a long-legged divertor. We argue that successful development and integration of these innovative and synergistic technologies would dramatically change the outlook for fusion, providing a real opportunity to positively impact global climate change and to reverse the loss of U.S. leadership in fusion research, suffered in recent decades. Table of Contents 1. Executive summary .............................................................................................................. 1 2. High Temperature Superconductors ................................................................................... 4 3. Demountable Superconducting Magnet Coils ..................................................................... 7 4. Molten-Salt Liquid Blankets ................................................................................................. 9 5. High-Field Launch RF for Heating and Current Drive ........................................................