Resonant Magnetic Perturbation Effect on the Tearing Mode Dynamics
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Numerical Studies of Magnetic Fluctuation-Induced Transport In
DOE/ER/54687-3 UW-CPTC 05-6 Numerical Studies of Magnetohydrodynamic Activity Resulting from Inductive Transients Final Report August 15, 2002 – August 14, 2005 C. R. Sovinec University of Wisconsin-Madison Madison, WI 53706 August 2005 THE U.S. DEPARTMENT OF ENERGY AWARD NO. DE-FG02-02ER54687 NOTICE This report was prepared as an account of work sponsored by the United States Government. Neither the United States nor the United States Department of Energy, nor any of their employees, nor any of their contractors, subcontractors, or their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility 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. Numerical Studies of Magnetohydrodynamic Activity Resulting from Inductive Transients U.S. Department of Energy, Office of Science, Contract DE-FG02-02ER54687 Final Report Principal Investigator: Carl Sovinec ([email protected]) Department of Engineering Physics, University of Wisconsin-Madison 1500 Engineering Drive, 519 ERB Madison, WI 53706-1609 1. Executive Summary This report describes results from numerical studies of transients in magnetically confined plasmas. The work has been performed by University of Wisconsin graduate students James Reynolds and Giovanni Cone and by the Principal Investigator through support from contract DE-FG02-02ER54687, a Junior Faculty in Plasma Science award from the DOE Office of Science. Results from the computations have added significantly to our knowledge of magnetized plasma relaxation in the reversed-field pinch (RFP) and spheromak. In particular, they have distinguished relaxation activity expected in sustained configurations from transient effects that can persist over a significant fraction of the plasma discharge. -
Alternative Pathways to Fusion Energy (Focus on Department of Energy Innovative Confinement Concepts)
Alternative pathways to fusion energy (focus on Department of Energy Innovative Confinement Concepts) S. Woodruff May 1st 2006 GCEP Fusion Energy Workshop, Princeton, NJ Thanks for help and permission: Brown Bauer Belova Siemon Cothran Hooper Jarboe Ellis Shumlak Hassam Slough Sarff Hoffman Ji Mauel Yamada Kesner Barnes Thio Wurden 1. Motivation: cutting edge plasma science and a paradigm shift for fusion. 2. Innovative confinement concepts: a) Doubly connected b) Simply connected closed c) Simply connected open d) Theory support 3. Culture of innovation 1. Motivation: cutting edge plasma science and a paradigm shift for fusion. 2. Innovative confinement concepts: a) Doubly connected b) Simply connected closed c) Simply connected open d) Theory support 3. Culturing innovation Innovative Confinement Concepts • Cutting-edge plasma science across the nation. • Experiments offer to fundamentally change the paradigm of Fusion Energy Sciences. • Experiments aim to operate in new plasma regimes. • Premier method to train the next generation of plasma researchers (more than 100 students/year). • The US program leads the world in concept innovation. • Small-scale experiments (<1-2M/year) deliver value science. Can we fundamentally change the paradigm? Yes! Think: complexity, scale and new physics. •To first order, the total weight Total cost of the fusion core is a measure Direct cost 65% indirect cost 25% of it’s cost. Contingency 10% 100% •‘Simply connected’ may be a Direct cost virtue. Reactor 50-60% Conventional plant 35-30% Structures 15-10% Doubly: a Ro 100% structure Reactor Cost links plasma Coils 30% Torus Shield 10% Blanket Blanket 10% Simply: a Heat Transfer 15% nothing Auxilliary power 15% links plasma Other compnents 20% CT 100% Fusion development path is staged to address scientific and performance metrics. -
Subject Categories and Scope Descriptions Co Q
International Nuclear Information System (INIS) • LU Q CD XA0202260 D) c CO IAEA-ETDE/TNIS-2 o X LU CO -I—• SUBJECT CATEGORIES AND SCOPE DESCRIPTIONS CO Q ETDE/INIS Joint Reference Series No. 2 CT O c > LU O O E "- =3 CO I? O cB CD C , LU • CD 3 CO -Q T3 CD >- c •a « C c CD o o CD «2 i- CO .3-3/33 CO ,_ CD a) O % 3 O •z. a. Renewable energy technologies • Radiation protection • Energy storage, conversion, and consumption Radioactive waste management • Energy policy • Radiation effects on living organisms • Fossil fuels INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, JULY 2002 ETDE/INIS Joint Reference Series No. 2 SUBJECT CATEGORIES AND SCOPE DESCRIPTIONS INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA, JULY 2002 SUBJECT CATEGORIES AND SCOPE DESCRIPTIONS IAEA, VIENNA, 2002 IAEA-ETDE/INIS-2 ISBN 92-0-112902-5 ISSN 1684-095X © IAEA, 2002 Printed by the IAEA in Austria July 2002 PREFACE This document is one in a series of publications known as the ETDE/INIS Joint Reference Series. It defines the subject categories and provides the scope descriptions to be used for categorization of the nuclear literature for the preparation of INIS input by national and regional centers. Together with volumes of the INIS Reference Series and ETDE/INIS Joint Reference Series it defines the rules, standards and practices and provides the authorities to be used in the International Nuclear Information System. A list of the volumes published in the IMS Reference Series and ETDE/ENIS Joint Reference Series can be found at the end of this publication. -
LA-7973-MS the Reversed-Field Pinch Reactor (RFPR) Concept O
LA-7973-MS Informal Report The Reversed-Field Pinch Reactor (RFPR) Concept 01 O LOS ALAMOS SCIENTIFIC LABORATORY Post Office Box 1663 Los Alamos. New Mexico 87545 LA-7973-MS Informal Report UC-20d MOT Issued: August 1979 The Reversed-Field Pinch Reactor (RFPR) Concept R. L. Hagenson R. A. Krakowski G. E. Cort MAJOR CONTRIBUTORS Engineering: W. E. Fox, R. W. Teasdale Neutronics: P. D. Soran Tritium: C. G. Bathke, H. Cullingford Materials: F. W. Clinard, Jr. Plasma Engineering: R. L. Miller Physics: D. A. Baker, J. N. DiMarco Electrotechnology: R. W. Moses l-neip. :«. makes s any legal inW,i» „. ,«p..nS*.lil> >"' <'« 11|lll.CSi Ulit l'ISCl • '' ! 1. Equilibrium and Stability 15b 2. Transport 155 3-. Startup . 158 4. Rundown (Quench) 159 B. T'jchnolofey Assessment 160 1. First wall 160 2. Blanket 160 3» Energy Transfer, Storage and Switching 161 4. Magnets 162 5« Vacuum and Tritium Recovery 162 C. Summary Assessment 163 APPENDIX A. RFPR BURN MODEL AND REACTOR'CODE 166 1. Plasma and Magnetic Field Models 166 2. Plasma Energy balance 169 3. Anomalous Radial Transport 17A APPENDIX B. COSTING MODEL 176 APPENDIX C. STANDARD FUSIOt: REACTOR DESIGN TABLE 185 APPENDIX D. BLANKET TRITIUM TRANSPORT MODEL 197 1. Development of Model 197 2. Evaluation of Model 200 3. Tritium Inventory Question - 202 APPENDIX E. SUMMARY REVIEW OF DESIGN POINT EVOLUTION 206 vn TABLE OF CONTENTS THL REVERSED-FIELI) PINCH REACTOR (KFPR) CONCEPT 1 ABSTRACT 1 I. INTRODUCTION 2 II. EXECUTIVE SUMMARY 4 A. Fundamental Physics Issues 4 B. Reactor Description ••* 9 1. Reactor Operation 10 2. -
The Titan Reversed-Field-Pinch Fusion Reactor Study
4X* I ^© tf> UCLA-PPG-1200 THE TITAN REVERSED-RELD-PINCH FUSION REACTOR STUDY gFVysw^Bijyp. Final Report 1990 Volume III: TITAN-I Fusion Power Core University of California, Los Angeles Los Alamos National Laboratory Department of Mechanical, Aerospace, Los Alamos, NM and Nuclear Engineering and Institute of Plasma and Fusion Research. Los Angeles, CA Rensselaer Polytechnic Institute General Atomics Department of Nuclear Engineering San Diego, CA Troy, NY ClSTRIBUTION OF THIS DOCUMENT IS UNLIMITED DISCLAIMER 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 agen cy thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or useful ness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately r-wned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommen dation, 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 State Government or any agency thereof. UCLA/PPG—1200-Vol .3 DE92 000139 THE TITAN REVERSED-FIELD-PINCH FUSION REACTOR STUDY FINAL REPORT 1090 Volume III: TITAN-I Fusion Power Core University of California, Los Angeles Los Alamos National Laboratory Department of MeehanicaJ, Aerospace, Los Alamos, NM and Nuclear Engineering and Institute of Plasma and Fusion Research Los Angeles, CA Rensselaer Polytechnic Institute General Atomics Department of Nuclear Engineering San Diego, Ca Troy, NY MASTER ^ DISTRIBUTION OF THIS DOCUMENT IS UNLIMITED CONTRIBUTING AUTHORS UNIVERSITY OF CALIFORNIA, LOS ANGELES Farrokh Najmabadi, Robert W. -
Electron Density Fluctuations and Fluctuation-Induced Transport in the Reversed-Field Pinch
ELECTRON DENSITY FLUCTUATIONS AND FLUCTUATION-INDUCED TRANSPORT IN THE REVERSED-FIELD PINCH by Nicholas E. Lanier A dissertation submitted in partial fulfillment of the requirements for the degree of Doctor of Philosophy (Physics) at the University of Wisconsin–Madison 1999 i ELECTRON DENSITY FLUCTUATIONS AND FLUCTUATION- INDUCED TRANSPORT IN THE REVERSED-FIELD PINCH Nicholas E. Lanier Under the supervision of Professor Stewart C. Prager At the University of Wisconsin–Madison An extensive study on the origin of density fluctuations and their role in particle transport has been investigated in the Madison Symmetric Torus reversed-field pinch. The principal physics goals that motivate this work are: investigating the nature of particle transport in a stochastic field, uncovering the relationship between density fluctuations and magnetic field fluctuations arising from tearing and reconnection, identifying the mechanisms by which a single tearing mode in a stochastic medium can affect particle transport. Following are the primary physics results of this work. Measurements of the radial electron flux profiles indicate that confinement in the core is improved during pulsed poloidal current drive experiments. Correlations between density and magnetic fluctuations demonstrate that the origin of the large amplitude density fluctuations can be directly attributed to the core-resonant tearing modes, and that these fluctuations are advective in the plasma edge; however, these fluctuations appear compressional in the core, provided the nonlinear terms are small. Correlations between density and radial velocity fluctuations indicate that although the fluctuations from the core-resonant modes dominate at the edge, their relative phase is such that they do not cause transport there, consistent with the expectation that core modes do not destroy edge magnetic surfaces. -
Electron Thermal Transport in the Madison Symmetric Torus
ELECTRON THERMAL TRANSPORT IN THE MADISON SYMMETRIC TORUS by THEODORE MATHIAS BIEWER A dissertation submitted in partial fulfillment of the requirements for the degree of DOCTOR OF PHILOSOPHY (PHYSICS) at the UNIVERSITY OF WISCONSIN-MADISON 2002 i Electron Thermal Transport in the Madison Symmetric Torus Theodore M. Biewer Under the supervision of Assistant Professor Cary B. Forest At the University of Wisconsin-Madison Abstract Due to diagnostic improvements and the development of the MSTFit equilibrium reconstruction code, it has become possible for the first time to accurately characterize the transport behavior of MST plasmas over the sawtooth cycle. Magnetic fluctuations in the MST reversed-field pinch, which rise sharply at the crash, play a significant role in the transport of heat and particles. The RFP configuration is a good test bed for studying magnetic fluctuation induced transport since the overlapping magnetic tearing mode islands create a large radial region in which the magnetic flux surfaces are destroyed and field lines wander stochastically. The measured electron thermal conductivity in this stochastic region agrees with Rechester-Rosenbluth like predictions from a fluctuating magnetic field. Time evolving profiles are measured to understand electron heat and particle transport in the MST. In particular, electron temperature, electron density, and current density profiles have been measured during a “Standard” plasma sawtooth cycle. The MHD activity during the sawtooth cycle is examined as an a priori, time-evolving condition that is affecting the plasma equilibrium and consequently the transport of heat and particles. The cause of the MHD behavior is not central to this thesis. Rather, the effects of the fluctuations on transport are considered. -
Sweep System Design for a Heavy Ion Beam Probe on Madison Symmetric Torus J
REVIEW OF SCIENTIFIC INSTRUMENTS VOLUME 70, NUMBER 1 JANUARY 1999 Sweep system design for a heavy ion beam probe on Madison Symmetric Torus J. Lei, T. P. Crowley, U. Shah, P. M. Schoch, K. A. Connor, and J. Schatz ECSE Department, Rensselaer Polytechnic Institute, Troy, New York 12180 ~Presented on 10 June 1998! The sweep system for the heavy ion beam probe on the Madison Symmetric Torus ~MST! is described. The two components of the system are the primary sweep optics and secondary collimation plates. Key issues in the sweep system design are the small entrance and exit ports available on MST, the significant toroidal beam motion induced by the strong poloidal magnetic field, and the excessive current loading due to plasma and ultraviolet ~UV!. The design accommodates these issues using a crossover sweep plate design in two dimensions for the primary beam as well as two dimensional sweeping on the secondary beam. The primary beam sweep design results in a sweep range of 620° in one direction and 65° in the perpendicular direction. The secondary beam sweep design results in entrance angles to the energy analyzer of ,3° in radial and ;0° in toroidal directions. The procedure for calculating sweep performance including fringe fields, a system for active trajectory control, and initial experiments on plasma and UV loading are also discussed. © 1999 American Institute of Physics. @S0034-6748~99!67001-0# I. INTRODUCTION normal. This in turn, results in a large required sweep angle range and increased exposure of the sweep plates to UV A heavy ion beam probe measures a variety of plasma radiation and plasma streaming out of the port. -
Nuclear Fusion Power – an Overview of History, Present and Future
International Journal of Advanced Network, Monitoring and Controls Volume 04, No.04, 2019 Nuclear Fusion Power – An Overview of History, Present and Future Stewart C. Prager Department of Physics University of Wisconsin – Madison Madison, WI 53706, USA E-mail: [email protected] Summary—Fusion power offers the prospect of an allowing the nuclei to fuse together. Such conditions almost inexhaustible source of energy for future can occur when the temperature increases, causing the generations, but it also presents so far insurmountable ions to move faster and eventually reach speeds high engineering challenges. The fundamental challenge is to enough to bring the ions close enough together. The achieve a rate of heat emitted by a fusion plasma that nuclei can then fuse, causing a release of energy. exceeds the rate of energy injected into the plasma. The main hope is centered on tokamak reactors and II. FUSION TECHNOLOGY stellarators which confine deuterium-tritium plasma In the Sun, massive gravitational forces create the magnetically. right conditions for fusion, but on Earth they are much Keywords-Fusion Energy; Hydrogen Power; Nuclear Fusion harder to achieve. Fusion fuel – different isotopes of hydrogen – must be heated to extreme temperatures of I. INTRODUCTION the order of 50 million degrees Celsius, and must be Today, many countries take part in fusion research kept stable under intense pressure, hence dense enough to some extent, led by the European Union, the USA, and confined for long enough to allow the nuclei to Russia and Japan, with vigorous programs also fuse. The aim of the controlled fusion research underway in China, Brazil, Canada, and Korea. -
20081106 FESAC Debriefing-V7
Report of the Toroidal Alternates Panel David N. Hill (Panel Chair) Lawrence Livermore National Laboratory Outline Charge from Under Secretary of Science Panel membership and process Panel findings: answers to the charge – General findings – Concept specific: o ITER-era goals o High-priority issues, gaps, and initiatives o Scientific benefits Website: http://fusion.gat.com/tap Presented to FESAC: November 6, 2008 This work performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under Contract DE-AC52-07NA27344. FESAC debriefing 11/6/08 v7 #1 Charge to FESAC From DoE Under Secretary for Science Focus on Four Toroidal Confinement Concepts – Spherical Torus, Stellarator, Reversed-Field Pinch, Compact Torus(FRC & spheromak) For those concepts that are seen to have promise for fusion energy, please identify and justify a long-term objective for each concept as a goal for the ITER era. – ITER era: when ITER operates (~ next 15-20 years) – Panel addressed all four – Iterative process with community to identify ITER-era goal – Reasonably ambitious and focused goals With that[goal] in mind, I ask that FESAC: 1 critically evaluate the goal chosen for each concept, and its merits for fusion development; 2 identify and prioritize scientific and technical questions that need to be answered to achieve the specified goal; 3 assess available means to address these questions; and 4 identify research gaps and how they may be addressed through existing or new facilities, theory and modeling/computation. Identify and prioritize the unique toroidal fusion science and technology issues that an alternate concept can address, independent of its potential as a fusion energy concept. -
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. -
Fifty Years of Magnetic Fusion Research (1958–2008): Brief Historical Overview and Discussion of Future Trends
Energies 2010, 3, 1067-1086; doi:10.3390/en30601067 OPEN ACCESS energies ISSN 1996-1073 www.mdpi.com/journal/energies Review Fifty Years of Magnetic Fusion Research (1958–2008): Brief Historical Overview and Discussion of Future Trends Laila A. El-Guebaly University of Wisconsin-Madison, 1500 Engineering Dr. Madison, WI 53706, USA; E-Mail: [email protected]; Tel.: +01-608-263-1623; Fax: +01-608-263-4499 Received: 3 March 2010; in revised form: 29 April 2010 / Accepted: 10 May 2010 / Published: 1 June 2010 Abstract: Fifty years ago, the secrecy surrounding magnetically controlled thermonuclear fusion had been lifted allowing researchers to freely share technical results and discuss the challenges of harnessing fusion power. There were only four magnetic confinement fusion concepts pursued internationally: tokamak, stellarator, pinch, and mirror. Since the early 1970s, numerous fusion designs have been developed for the four original and three new approaches: spherical torus, field-reversed configuration, and spheromak. At present, the tokamak is regarded worldwide as the most viable candidate to demonstrate fusion energy generation. Numerous power plant studies (>50), extensive R&D programs, more than 100 operating experiments, and an impressive international collaboration led to the current wealth of fusion information and understanding. As a result, fusion promises to be a major part of the energy mix in the 21st century. The fusion roadmaps developed to date take different approaches, depending on the anticipated power plant concept and the degree of extrapolation beyond ITER. Several Demos with differing approaches will be built in the US, EU, Japan, China, Russia, Korea, India, and other countries to cover the wide range of near-term and advanced fusion systems.