Book of Abstracts Contribution: T1 / Beam Plasmas and Inertial Fusion

Total Page:16

File Type:pdf, Size:1020Kb

Book of Abstracts Contribution: T1 / Beam Plasmas and Inertial Fusion Book of Abstracts Contribution: T1 / Beam Plasmas and Inertial Fusion Exploring HED physics, ICF dynamics and lab astrophysics with advanced nuclear diagnostics Chikang Li Massachusetts Institute of Technology, Cambridge, MA 02139, USA Significant progress has recently been made in developing advanced nuclear diagnostics for the OMEGA laser facility and the National Ignition Facility (NIF). Both self-emitted fusion products and backlighting nuclear particles have been measured and used to study a large range of basic physics of high-energy-density (HED) plasmas. The highlights of these achievements are manifested by numerous recent publications. For ignition science in inertial-confinement fusion (ICF) experiments, for example, these works have helped to advance our understanding of kinetic effects in exploding-pusher ICF implosions and our understanding of NIF capsule implosion dynamics and symmetry. For basic physics in HED plasmas and laboratory astrophysics, our research contributed to the understanding of nuclear plasma science, the generation and reconnection of self-generated spontaneous electromagnetic fields and associated plasma instabilities, high-Mach-number plasma jets, Weibel-mediated electromagnetic collisionless shocks, and charged-particle stopping power in various laser-produced HED plasmas. In this Tutorials and Topical Lecture, we will present details of these researches. The work described herein was performed in part at the LLE National Laser User’s Facility (NLUF), and was supported in part by US DOE, LLNL and LLE. 3rd European Conference on Plasma Diagnostics (ECPD), 6-9 May 2019, Lisbon, Portugal https://www.ipfn.tecnico.ulisboa.pt/ECPD2019/ Contribution: T2 / Basic and Astrophysical Plasmas Detection of the missing baryons by studying the lines from the Warm Hot Intergalactic Medium (WHIM) F. Nicastro INAF - Osservatorio Astronomico di Roma It has been known for decades that the observed number of baryons in the local Universe falls about 30-40% short of the total number of baryons predicted by Big-Bang Nucleosynthesis, inferred by density fluctuations of the Cosmic Microwave Background and seen during the first 2-3 billion years of the universe (redshift z>2-3) in the so called “Lyman-α Forest". While theory provides a reasonable solution to this paradox, by locating the missing baryons in hot and tenuous filamentary gas connecting galaxies, it also sanctions the difficulty of detecting them because their by far largest constituent, hydrogen, is mostly ionized and therefore virtually invisible in ordinary signal-to-noise Far-Ultraviolet spectra. Indeed, despite the large observational efforts, only a few marginal claims of detection have been made so far. Here I will first review the observational efforts pursued over the past 15 years by several groups and will then present our recent results that show that the missing baryons are indeed found in a tenuous warm-hot and moderately enriched medium that traces large concentrations of galaxies and permeates the space between and around them. The detection of these baryons is hampered by foreground ISM contamination, which is hard to correct for, due to our poor knowledge of inner-shell resonant transitions from metals in the X-ray band. Despite these intrinsic difficulties, I will show that the number of OVII systems detected down to the sensitivity threshold of our data, agrees well with numerical simulation predictions for the long-sought hot intergalactic medium, and its detection adds a fundamental tile to the long-standing missing baryon puzzle. Finally, I will comment on the implications of these new results for future high resolution X-ray missions. 3rd European Conference on Plasma Diagnostics (ECPD), 6-9 May 2019, Lisbon, Portugal https://www.ipfn.tecnico.ulisboa.pt/ECPD2019/ Contribution: T3 / Magnetic Confinement Fusion Bolometer Developments in Diagnostics for Magnetic Confinement Fusion H. Meister1, M. Bernert1, W. Biel2, L.C. Ingesson3, B.J. Peterson4, R. Reichle5, M.L. Reinke6, S. Schmitt7, D. Zhang8 1 Max-Planck-Institut für Plasmaphysik, Garching, Germany 2 Forschungszentrum Jülich, Jülich, Germany 3 Fusion for Energy, Barcelona, Spain 4 National Institute for Fusion Science, Toki, Japan 5 ITER Organisation, St. Paul-les-Durance, France 6 Oak Ridge National Laboratory, USA 7 Fraunhofer-IMM, Mainz, Germany 8 Max-Planck-Institut für Plasmaphysik, Greifswald, Germany The plasma radiation is an essential part of the energy balance in current and future magnetic confinement fusion experiments and gives crucial insight for the challenges of power exhaust and divertor detachment as well as valuable information to understand plasma instabilities and transport effects. It is typically measured using various types of bolometers. Present day experimental devices, both the tokamak and stellarator, make use of metal resistor bolometers and IR video bolometers (IRVB), depending on the main focus of the respective measurement. The well-established sensor for absolutely calibrated measurements is the metal resistor bolometer. AXUV diodes, often used in conjunction with bolometers, are ideal for observing fast transient events in a plasma due to their very short response times, but their sensitivity varies significantly over the full radiation spectrum and degrades over time. In cases where many lines-of-sight are needed to observe radiation profiles in complex geometries IRVB offers the ability to integrate high channel counts in rather narrow installation volumes. These diagnostic concepts are presented as well as their pros and cons using examples of measurements from various devices like ASDEX Upgrade, JET, LHD and Wendelstein 7-X. For future devices like ITER and DEMO, new developments are required to adapt sensors and diagnostic schemes to the harsh nuclear environment. An overview will be given over the activities for sensor development and integration challenges, which may also be relevant for long pulse operation in present experiments. 3rd European Conference on Plasma Diagnostics (ECPD), 6-9 May 2019, Lisbon, Portugal https://www.ipfn.tecnico.ulisboa.pt/ECPD2019/ Contribution: T4 / Beam Plasmas and Inertial Fusion Optical diagnostics: femtosecond laser measurements of E fields and novel methods for temperature and pressure measurements with atomic and molecular Richard Miles Department of Aerospace Engineering, Texas A&M University Department of Mechanical and Aerospace Engineering, Princeton University. Understanding the detailed mechanisms associated with time varying nonequilibrium plasmas is of importance for controlled ignition of combusting gases, electric propulsion, chemical processing, flashlamp and laser operation, breakdown suppression, hypersonic flight and, increasingly, for medical applications. Studying the dynamics of these plasmas requires stand-off approaches since conventional probes cause significant perturbations. Local parameters of importance are the electron density and temperature, electric field, ionization and dissociation fractions, molecular vibrational, rotational and kinetic temperature. Several new laser based methods are now being developed to enable measurements of these parameters. For example, electric-field induced second harmonic generation (E-FISH)] is able to provide sub nanosecond time resolved measurement of the local electric field by focusing a short pulse (picosecond or femtosecond) laser to the measurement point and detecting the second harmonic light produced by the nonlinear interaction of the laser with the electric field and the ambient gas or plasma. Femtosecond laser driven two photon absorption laser induced fluorescence (TALIF) and resonant ionization followed by microwave scattering (Radar REMPI) are also effective approaches to the measurement of ions and dissociated species. With nanosecond pulsed frequency tunable lasers, atomic filters and molecular filters can be used to suppress background scattering and select for specific molecular species and energy states. For example, slow light imaging spectroscopy (SLIS) takes advantage of atomic resonant induced dispersion for imaging Raman scattering spectra through time delayed propagation of the selected spectral feature. With proper choice of filters and laser wavelength, pressure can also be measured. The presentation will focus on recently developed methods that are useful for the measurement of rapidly time varying, localized, partially ionized plasmas. 3rd European Conference on Plasma Diagnostics (ECPD), 6-9 May 2019, Lisbon, Portugal https://www.ipfn.tecnico.ulisboa.pt/ECPD2019/ Contribution: I1.1 / Low-Temperature and Industrial Plasmas In situ and remote laser diagnostics for material characterization from plasma facing components to Cultural Heritage surfaces Roberta Fantoni ENEA – FSN-TECFIS C.R. Frascati, Via Enrico Fermi 45, 00044 Frascati, (Rome), Italy Optical and spectroscopic techniques offer unique possibilities for non destructive or microdestructive characterization of surfaces, with widespread applications, starting from in-line monitoring of industrial processes. A significant group of industrial applications concerns nuclear grade material characterization and plasma diagnostics relevant to the thermonuclear fusion process. However, technologies and methodologies originally developed for specific in-vessel utilization, can easily find additional in-situ and remote application to environmental and cultural heritage diagnostics addressed to preventive conservation and restoration of surfaces. The development
Recommended publications
  • Engineering Optimization of Stellarator Coils Lead to Improvements in Device Maintenance
    2015 IEEE 26th Symposium on Fusion Engineering (SOFE 2015) Austin, Texas, USA 31 May – 4 June 2015 IEEE Catalog Number: CFP15SOF-POD ISBN: 978-1-4799-8265-3 Copyright © 2015 by the Institute of Electrical and Electronics Engineers, Inc All Rights Reserved Copyright and Reprint Permissions: Abstracting is permitted with credit to the source. Libraries are permitted to photocopy beyond the limit of U.S. copyright law for private use of patrons those articles in this volume that carry a code at the bottom of the first page, provided the per-copy fee indicated in the code is paid through Copyright Clearance Center, 222 Rosewood Drive, Danvers, MA 01923. For other copying, reprint or republication permission, write to IEEE Copyrights Manager, IEEE Service Center, 445 Hoes Lane, Piscataway, NJ 08854. All rights reserved. ***This publication is a representation of what appears in the IEEE Digital Libraries. Some format issues inherent in the e-media version may also appear in this print version. IEEE Catalog Number: CFP15SOF-POD ISBN (Print-On-Demand): 978-1-4799-8265-3 ISBN (Online): 978-1-4799-8264-6 ISSN: 1078-8891 Additional Copies of This Publication Are Available From: Curran Associates, Inc 57 Morehouse Lane Red Hook, NY 12571 USA Phone: (845) 758-0400 Fax: (845) 758-2633 E-mail: [email protected] Web: www.proceedings.com TABLE OF CONTENTS ENGINEERING OPTIMIZATION OF STELLARATOR COILS LEAD TO IMPROVEMENTS IN DEVICE MAINTENANCE ..................................................................................................................................................1 T. Brown, J. Breslau, D. Gates, N. Pomphrey, A. Zolfaghari NSTX TOROIDAL FIELD COIL TURN TO TURN SHORT DETECTION .................................................................7 S. Ramakrishnan, W.
    [Show full text]
  • Time Evaluation of Diamagnetic Loop and Mirnov Oscillations in a Major Plasma Disruption and Comparison with a Normal Shot
    International Nano Letters https://doi.org/10.1007/s40089-018-0259-x ORIGINAL ARTICLE Time evaluation of diamagnetic loop and Mirnov oscillations in a major plasma disruption and comparison with a normal shot R. Sadeghi1 · Mahmood Ghoranneviss1 · M. K. Salem1 Received: 21 November 2018 / Accepted: 7 December 2018 © The Author(s) 2018 Abstract In this paper, plasma disruption was investigated in IR-T1 tokamak. Moreover, the time evaluation of plasma parameters such as plasma current, Ip; loop voltage, Vloop; power heating; and safety factor was illustrated. The results of diamagnetic loop and Mirnov oscillations in a major disruption were compared with their results in a normal shot. In addition, plasma disruption in diferent tokamaks was investigated and the results were compared with the IR-T1 tokamak. Keywords Disruption · Runaway electrons · Mirnov coils · Diamagnetic loop · Tokamak · MHD instability Introduction tokamak disruptions cause plasma confinement to be destroyed by restriction of current and density which ends Among various tools of magnetic confnement, tokamak to large mechanical stresses. Plasma disruption is caused containing hot plasma is one of the best and developed by strong stochastic magnetic feld formed due to nonlin- devices [1]. Tokamaks are divided into two groups: frst, the earity excited low-mode number magneto–hydro–dynamics large tokamaks for studying large plasmas such as DIII-D (MHD) modes. The safety factor (q) is very important in [2] and Tore–Supra [3] with high-cost testing conditions and determining stability and transport theory [9–13]. The paper second, small tokamaks such as STOR-M [4] and ISTTOK is organized as follows: in Sect.
    [Show full text]
  • Edge Turbulence in ISTTOK: a Multi-Code Fluid Validation B Dudson, W Gracias, R Jorge, a Nielsen, J Olsen, P Ricci, C Silva, P
    Edge turbulence in ISTTOK: a multi-code fluid validation B Dudson, W Gracias, R Jorge, A Nielsen, J Olsen, P Ricci, C Silva, P. Tamain, G. Ciraolo, N Fedorczak, et al. To cite this version: B Dudson, W Gracias, R Jorge, A Nielsen, J Olsen, et al.. Edge turbulence in ISTTOK: a multi-code fluid validation. Plasma Physics and Controlled Fusion, IOP Publishing, 2021. hal-03179634 HAL Id: hal-03179634 https://hal.archives-ouvertes.fr/hal-03179634 Submitted on 24 Mar 2021 HAL is a multi-disciplinary open access L’archive ouverte pluridisciplinaire HAL, est archive for the deposit and dissemination of sci- destinée au dépôt et à la diffusion de documents entific research documents, whether they are pub- scientifiques de niveau recherche, publiés ou non, lished or not. The documents may come from émanant des établissements d’enseignement et de teaching and research institutions in France or recherche français ou étrangers, des laboratoires abroad, or from public or private research centers. publics ou privés. Edge turbulence in ISTTOK: a multi-code fluid validation B. D. Dudson1, W. A. Gracias2, R. Jorge3;4, A. H. Nielsen5, J. M. B. Olsen5, P. Ricci3, C. Silva4, P. Tamain6, G. Ciraolo6, N. Fedorczak6, D. Galassi3;7, J. Madsen5, F. Militello8, N. Nace6, J. J. Rasmussen5, F. Riva3;8, E. Serre7 1York Plasma Institute, Department of Physics, University of York YO10 5DQ, UK 2Universidad Carlos III de Madrid, Leganés, 28911, Madrid, Spain 3École Polytechnique Fédérale de Lausanne (EPFL), Swiss Plasma Center (SPC), CH-1015 Lausanne, Switzerland 4Instituto de Plasmas e Fusão Nuclear, Instituto Superior Técnico, Universidade de Lisboa, 1049-001 Lisboa, Portugal 5Department of Physics, Technical University of Denmark, Fysikvej, DK-2800 Kgs.-Lyngby, Denmark 6IFRM, CEA Cadarache, F-13108 St.
    [Show full text]
  • Tokamak Energy April 2019
    Faster Fusion through Innovations M Gryaznevich and Tokamak Energy Ltd. Team FusionCAT Webinar 14 September 2020 © 2020 Tokamak Energy Tokamak 20202020 © Energy Tokamak Fusion Research – Public Tokamaks JET GLOBUS-M Oxford, UK StPetersburg, RF COMPASS KTM Prague, CZ (1) Kurchatov, KZ (3) T15-M Alcator C-Mod Moscow STOR-M Cambridge, MA MAST Saskatoon, SK Oxford, UK ASDEX KSTAR ITER(1)(2) / WEST Garching, DE Daejeon, KR LTX / NSTX Cadarache, FR FTU HL-2 (1) Pegasus Princeton, NJ Frascati, IT JT-60SA DIII-D Madison, WI TCV Chengdu, CN QUEST Naka, JP San Diego, CA ISTTOK Lausanne, CH Kasuga, JP Lisbon, PT SST-1 / ADITY EAST Gandhinagar, IN Hefei, CN Conventional Tokamak • Fusion research is advancing Spherical Tokamak • However, progress towards Fusion Power is constrained Note: Tokamaks are operating unless indicated otherwise. (1) Under construction. (2) The International Thermonuclear Experimental Reactor (“ITER”) megaproject is supported by China, the European Union, India, Japan, Korea, Russia and the United States. © 2020© Energy Tokamak (3) No longer in use. 2 Fusion Development – Private Funding Cambridge, MA Langfang, PRC Vancouver, BC Los Angeles, CA Orange County, CA • Common goal of privately and publicly Oxford, UK Oxford, UK funded Fusion research is to develop technologies and Fusion Industry • At TE, we have identified the key technology Conventional Tokamak Spherical Tokamak gaps needed to create a commercial fusion Non-Tokamak Technology reactor and then used Technology Roadmapping as an approach chart our path. © 2020©
    [Show full text]
  • Interface of EPICS with Marte for Real-Time Application
    1 Interface of EPICS with MARTe for Real-time Application October 23, 2012 Sangwon Yun Interface of EPICS with MARTe for Real-time Applications, October 23, 2012 2 Outlines Introduction ITER Task Overview of main technical subjects Multi-threaded Application Real-Time executor (MARTe) Portable Channel Access Server (pCAS) Interface of EPICS with MARTe The result of performance evaluation of MARTe Conclusions Acknowledgements and references Interface of EPICS with MARTe for Real-time Applications, October 23, 2012 3 Introduction ITER Task CODAC HPC (High Performance Computer) Dedicated computers running plasma control algorithms The Plasma Control System(PCS) requires the hard real-time operation The hard real-time control system requires the predictability in response time and deterministic upper bound in latency. In this regard, RTOS and real-time software framework are required to achieve those ITER Task : Evaluation and Demonstration of ITER CODAC Technologies at KSTAR Subtask : Implement density feedback control and verify its performance in a running device • To collect elements for decision making on PCS software framework • Deploy different PCS software framework based on KSTAR PCS on modified Linux and MARTe on RTOS for comparison KSTAR PCS Modified Linux RTOS (Based on RHEL) (MRG Realtime) See: Fast Controller Workshop, Feb 28, 2011. ITER IO Interface of EPICS with MARTe for Real-time Applications, October 23, 2012 4 Introduction MARTe framework for Hard Real-time Control System MARTe is a solution to be considered for a Real-time control system • The three considered system histogram The optimized reference program EPICS IOC MARTe application • Test conditions Run the system by providing an external sampling clock of 1 kHz 30,000 cycles Priority of the thread for ADC has been set to Latency distribution the highest CPU affinity (excepts EPICS IOC) • Result Reference EPICS IOC MARTe MARTe provides a shorter and, above all, Prog.
    [Show full text]
  • Imaging and Probe Techniques for Wave Dispersion Estimates in Magnetized Plasmas
    Imaging and Probe Techniques for Wave Dispersion Estimates in Magnetized Plasmas by A. D. Light B.A./B.S., Case Western Reserve University, 2005 A thesis submitted to the Faculty of the Graduate School of the University of Colorado in partial fulfillment of the requirements for the degree of Doctor of Philosophy Department of Physics 2013 This thesis entitled: Imaging and Probe Techniques for Wave Dispersion Estimates in Magnetized Plasmas written by A. D. Light has been approved for the Department of Physics Prof. Tobin Munsat Prof. Martin Goldman Date The final copy of this thesis has been examined by the signatories, and we find that both the content and the form meet acceptable presentation standards of scholarly work in the above mentioned discipline. Light, A. D. (Ph.D., Physics) Imaging and Probe Techniques for Wave Dispersion Estimates in Magnetized Plasmas Thesis directed by Prof. Tobin Munsat Fluctuations in magnetized laboratory plasmas are ubiquitous and complex. In addition to deleterious effects, like increasing heat and particle transport in magnetic fusion energy devices, fluctuations also provide a diagnostic opportunity. Identification of a fluctuation with a particular wave or instability gives detailed information about the properties of the underlying plasma. In this work, diagnostics and spectral analysis techniques for fluctuations are developed and applied to two different laboratory plasma experiments. The first part of this dissertation discusses imaging measurements of coherent waves in the Controlled Shear Decorrelation Experiment (CSDX) at the University of California, San Diego. Visible light from ArII line emission is collected at high frame rates using an intensified digital camera.
    [Show full text]
  • EX/P5-8 Effects of Viscosity on Magnetohydrodynamic Behaviour
    1 EX/P5-8 Effects of Viscosity on Magnetohydrodynamic Behaviour During Limiter Biasing on the CT-6B Tokamak P. Khorshid 1), L. Wang 2), M. Ghoranneviss 3), X.Z. Yang 2), C.H. Feng 2) 1) Department of Physics, Islamic Azad University, Mashhad, Iran, 2) Institute of Physics, Chinese Academy of Sciences, Beijing, China 3) Plasma Physics Research Center, Islamic Azad University, Tehran, Iran E-mail: [email protected] Abstract. Effects of viscosity on magnetohydrodynamics behaviour during limiter biasing in the CT-6B Tokamak has been investigated. The results shown that subsequent to the application of a positive bias, a decrease followed by an increase in the frequency of magnetic field fluctuations was observed. With contribution of viscous force effects in the radial force balance equation for Limiter Biasing, in terms of the nonstationarity model, it allows us to identify the understanding physics responsible for change in the Mirnov oscillations that could be related to poloidal rotation velocity and radial electric field. It could be seen that the time scale of responses to biasing is important. The response of ∇pi, decrease of poloidal rotation velocity, the edge electrostatics and magnetic fluctuations to external field have been investigated. The results shown that momentum balance equation with considering viscous force term can be use for modeling of limiter biasing in the tokamak. 1. Introduction Many experiments have shown the importance of the radial electric field in improved confinement states and several theories can explain the transition mechanism. There are several methods for controlling the radial electric field externally [1,2]. Edge biasing experiments have been found to be important in modifying edge turbulence and transport, but the mechanism of biasing penetration in edge fluctuations and its levels are different with respect to devices operation.
    [Show full text]
  • THE BIG STEP from ITER to DEMO J. Ongena , R.Koch, Ye.O
    THE BIG STEP FROM ITER TO DEMO J. Ongena , R.Koch, Ye.O.Kazakov Laboratorium voor Plasmafysica - Laboratoire de Physique des Plasmas Koninklijke Militaire School - Ecole Royale Militaire Association"EURATOM - Belgian State", B-1000 Brussels, Belgium Partner in the Trilateral Euregio Cluster (TEC) N. Bekris European Fusion Development Agreement JET Close Support Unit, Culham Science Centre Culham, OX14 3DB, United Kingdom D.Mazon Institut de Recherche sur la Fusion par Confinement Magnetique CEA Cadarache, 13108 St Paul-lez-Durance, France ABSTRACT ITER. Reactor studies are also being developed for Helical Devices (see e.g. [1-4]). However, a decision on a next step Extrapolation of the knowledge base towards a future stellarator/helical device can only take place when the main fusion power reactor is discussed. Although fusion research results of the current large helical devices in operation or has achieved important milestones since the start and construction have been obtained. The largest helical device continues achieving successes, we show that there are still currently in operation is LHD (Large Helical Device, in the important challenges that have to be addressed before the National Institute for Fusion Science (NIFS), close to construction and operation of an economical fusion power Nagoya, Japan). The construction of the largest stellarator reactor. Both physics and technological questions have to in the world Wendelstein 7-X (Max-Planck Institute, be solved. ITER is a significant step that will lead to major Greifswald, Germany) is nearly finished with first progress; for a DEMO reactor however, there will still be operations foreseen for beginning 2015. In this paper, we outstanding physics and engineering questions that require will therefore restrict ourselves to the discussion of a further R&D.
    [Show full text]
  • European Consortium for the Development of Fusion Energy European Consortium for the Development of Fusion Energy CONTENTS CONTENTS
    EuropEan Consortium for thE DEvElopmEnt of fusion EnErgy EuropEan Consortium for thE DEvElopmEnt of fusion EnErgy Contents Contents introDuCtion ReseaRCH units CooRDinating national ReseaRCH FoR euRofusion 16 agenzia nazionale per le nuove tecnologie, l’energia e lo sviluppo economico sostenibile (enea), italy euRofusion: eMboDying tHe sPiRit oF euRoPean CollaboRation 17 FinnFusion, finland 4 the essence of fusion 18 fusion@Öaw, austria the tantalising challenge of realising fusion power 19 hellenic fusion research unit (Hellenic Ru), greece the history of European fusion collaboration 20 institute for plasmas and nuclear fusion (iPFn), portugal 5 Eurofusion is born 21 institute of solid state physics (issP), latvia the road from itEr to DEmo 22 Karlsruhe institute of technology (Kit), germany 6 Eurofusion facts at a glance 23 lithuanian Energy institute (lei), lithuania 7 itEr facts at a glance 24 plasma physics and fusion Energy, Department of physics, technical university of Denmark (Dtu), Denmark JEt facts at a glance 25 plasma physics Department, wigner Fusion, hungary 8 infographic: Eurofusion devices and research units 26 plasma physics laboratory, Ecole royale militaire (lPP-eRM/KMs), Belgium 27 ruder Boškovi´c institute, Croatian fusion research unit (CRu), Croatia 28 slovenian fusion association (sFa), slovenia 29 spanish national fusion laboratory (lnF), CiEmat, spain 30 swedish research Council (vR), sweden rEsEarCh unit profilEs 31 sylwester Kaliski institute of plasma physics and laser microfusion (iPPlM), poland 32 the institute
    [Show full text]
  • Book of Abstracts
    16th Latin American Workshop on Plasma Physics LAWPP 2017 Universidad Nacional Autónoma de México Mexico City 4-8 September Book of Abstracts SPONSORS UNIVERSIDAD NACIONAL AUTÓNOMA DE MÉXICO Coordinación de la Instituto de Instituto de Investigaciones Investigación Científica Ciencias Nucleares en Materiales Facultad de Ciencias Instituto de Geofísica Instituto de Ciencias Físicas INSTITUTE OF SOCIEDAD MEXICANA DE FÍSICA CONSEJO NACIONAL DE ELECTRICAL AND CIENCIA Y TECNOLOGÍA ELECRONIC ENGINEERS INSTITUTO NACIONAL DE INVESTIGACIONES NUCLEARES CICATA-Qro INSTITUTO POLITÉCNICO NACIONAL i Talks at the Instituto de Ciencias Nucleares Talks at the Instituto de Investigaciones en Materiales * Graef Fernández Auditorium, at the Amoxcalli building, Facultad de Ciencias ** Lobby of the Amoxcalli building, Facultad de Ciencias For more information please check the Workshop Webpage http://WWW.nucleares.unam.mx/LAWPP2017 ii International Advisory Committee María Virginia Alves Instituto Nacional de Pesquisas Brazil Espaciais Luis Bilbao Universidad de Buenos Aires Argentina Iberê Caldas Universidade de São Paulo Brazil Luis Felipe Delgado-Aparicio Princeton Plasma Physics Peru and USA Laboratory Edberto Leal-Quirós University of California at Puerto Rico and Merced USA Daniel López-Bruna CIEMAT Spain George Morales University of California at USA Los Angeles AntHony Peratt Los Alamos National Laboratory USA Julio Puerta Universidad Simón Bolivar Venezuela Henry Riascos Universidad Tecnológica de Pereira Colombia Ramón Rodríguez Instituto de Geofísica
    [Show full text]
  • A Roadmap to the Realization of Fusion Energy
    Fusion Electricity A roadmap to the realisation of fusion energy Annexes Table of content Annex 1. Mission 1 - Plasma regimes of operation of a fusion power plant Annex 2. Mission 2 - Heat and particle exhaust Annex 3. Mission 3 - Neutron resistant materials Annex 4. Mission 4 - Tritium self-sufficiency and fuel cycle Annex 5. Mission 5 - Implementation of fusion safety aspects. Annex 6. Mission 6 - Integrated DEMO design and system development Annex 7. Mission 7 - Competitive cost of electricity. Annex 8. Mission 8 - Stellarator development Annex 9. Education and training needs in support of the EU fusion roadmap Annex 10. Opportunities for basic research Annex 11. Resources and implementation scheme Annex 12. Industrial involvement in the realization of fusion as an energy source Annex 13. International collaborations for the development of Fusion Energy Annex 14. Risk Register (internal use only) Annex 15. Work Packages (internal use only) Annex 16. Roadmap Gantt chart (internal use only) 2 Annex 1. Mission 1 - Plasma regimes of operation of a fusion power plant Authors: L. Horton (EFDA CSU), G. Sips (EFDA CSU), R. Neu (EFDA CSU) 1.1 Short description. In a fusion power plant, plasma regimes need to ensure a high fusion gain Q (Q=Pfus/Paux). The Lawson criterion sets a limit on the nτE product (with n the density and τE the energy confinement time) to achieve a given fusion gain. The energy confinement time is determined by plasma turbulence that has been progressively controlled by developing of more advanced regimes of operation. Our present understanding of transport processes in plasmas shows that the nτE product increases with the power plant dimension.
    [Show full text]
  • Fusion Energy Conference 2006 Book of Abstracts
    Fusion Energy Conference 2006 Book of Abstracts Contents Overview (OV) 1 OV/1-1 · Overview progress and future plan of EAST Project . 2 OV/1-2 · Overview of JT-60U Results for Development of Steady-State Advanced Toka- mak Scenario . 2 OV/1-3 · Overview of JET Results . 2 OV/1-4 · Development in the DIII-D Tokamak of Advanced Operating Scenarios and Associated Control Techniques for ITER . 3 OV/2-1 · Extended Steady-State and High-Beta Regimes of Net-Current Free Heliotron Plasmas in the Large Helical Device . 3 OV/2-2 · Overview of ASDEX Upgrade Results . 4 OV/2-3 · Overview of Physics Results from MAST . 4 OV/2-4 · Recent Physics Results from the National Spherical Torus Experiment . 5 OV/3-1 · Integration of High Power, Long Pulse Operation in Tore Supra in Preparation for ITER . 5 OV/3-2 · Overview of Alcator C-Mod Research Program . 6 OV/3-3 · Overview of TCV Results . 6 OV/3-4 · Overview of the FTU results . 7 OV/4-1 · Overview of HL-2A Experiment Results . 7 OV/4-2 · Overview of TJ-II experiments . 8 OV/4-3 · Overview of T-10 Results . 8 OV/4-4 · Experimental Progress on Zonal Flow Physics in Toroidal Plasmas . 8 OV/5-1 · Recent Progress on FIREX Project and Related Fusion Researches at ILE, Osaka 9 OV/5-2 · Overview of Inertial Fusion Research in the United States . 9 OV/5-3 · Theory of Alfv´enwaves and energetic particle physics in burning plasmas . 9 OV/5-4 · Status of R&D Activities on Materials for Fusion Power Reactors .
    [Show full text]