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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. -
Novel Concept for Disruption Mitigation in the ADITYA
28th IAEA Fusion Energy Conference (FEC 2020) Contribution ID: 1290 Type: Regular Poster Novel Concept for Disruption Mitigation in the ADITYA - U tokamak by Fast Time Response Electromagnetic Driven Pellet Impurity Injector Wednesday, 12 May 2021 17:00 (20 minutes) Implementation of suitable disruption mitigation technique remains the topmost priority for larger tokamaks including the ITER. The spontaneous disruption in ITER may probably be an unavoidable part, while operated with high performance D-T fuel [1]. Disruptions in ITER could produce very large heat loads on divertor tar- gets and other Plasma Facing Components (PFC), and large electromagnetic forces on the Vacuum Vessel (VV) can lead to structural damages [2]. In order to avoid these detrimental consequences, disruption mitigation is an essential part of tokamak research. The disruption mitigation system (DMS) in ITER is based on massive gas injection (MGI) of impurities, in order to radiate the plasma stored energy and mitigate the potentially damaging effects of disruptions [3]. Although, MGI based technique is suitable for most disruption mitiga- tion, there will be issues in case of having warning time less than 10 ms as may be the case for the onset of some disruptions in ITER [4]. This is due to the slow thermal velocity of the heavier impurity gas molecules, which limits the time needed to travel the distances before it reaches the plasma edge. At present, none of the currently planned disruption mitigations systems for ITER can respond on this time scale. The radiative dissipation of the plasma stored energy during major disruption in ITER by fast injection of massive pellets of low Z impurities, such as Li and Be pellet injection has been numerically modelled by Lukash et al. -
Overview of Recent Experimental Results from ADITYA Tokamak R
Tanna DOI:10.1088/1741-4326/aa6452 OV/4-3Rb Overview of Recent Experimental Results from ADITYA Tokamak R. Tanna1, J. Ghosh1, P. K. Chattopadhyay1, H. Raj1, S. Patel1, C. Gupta1, P. Dhyani2, K. A. Jadeja1, K. M. Patel1, S. B. Bhatt1, V. K. Panchal1, N. C. Patel1, C. Chavda1, E. V. Praveenlal1, K. S. Shah1, M. N. Makwana1, S. K. Jha1, M. V. Gopalakrishna1, K. Tahiliani1, D. Sangwan1, D. Raju1, U. C. Nagora1, S. K. Pathak1, P. K. Atrey1, S. Purohit1, Y. S. Joisa1, J. V. Raval1, C. V. S. Rao1, M. B. Chowdhuri1, S. Banerjee1, J. Thomas1, N. K. Ramaiya1, R. Manchanda1, A. Kumar1, P. K. Sharma1, S. V. Kulkarni1, K. Sathyanarayana1, B. K. Shukla1, A. Das1, R. Jha1, Y. C. Saxena1, A. Sen1, P. K. Kaw1, and D. Bora1 Rapporteured by: S. Pradhan 1Institute for Plasma Research (IPR), Bhat, Gandhinagar, India 2Ulsan National Institute of Science and Technology (UNIST), Ulsan, Republic of Korea Corresponding Author: R. Tanna, [email protected] Several experiments, related to controlled thermonuclear fusion research and highly relevant for large size tokamaks including ITER, have been carried out in ADITYA, an ohmically heated circular limiter tokamak. Repeatable plasma discharges of maximum plasma current of „160 kA and discharge duration beyond „250 ms with plasma current flattop duration of „140 ms has been obtained for the first time in ADITYA. The discharge reproducibility has been improved considerably with Lithium wall conditioning and improved plasma discharges are obtained by precisely controlling the plasma position. In these discharges, chord-averaged electron density „3:0–4:0 ˆ 1019{m3 using multiple hydrogen gas puffs, electron temperature of the order of „500– 700 eV have been achieved. -
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. -
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. -
Modeling of the Hα Emission from ADITYA Tokamak Plasmas
atoms Article Modeling of the Hα Emission from ADITYA Tokamak Plasmas Ritu Dey 1,*, Malay B. Chowdhuri 1 , Joydeep Ghosh 1,2, Ranjana Manchanda 1, Nandini Yadava 3 , Umeshkumar C. Nagora 1,2, Parveen K. Atrey 1, Jayesh V. Raval 1, Y. Shankara Joisa 1, Rakesh L. Tanna 1 and ADITYA Team 1 1 Institute for Plasma Research, Bhat, Gandhinagar 382 428, India; [email protected] (M.B.C.); [email protected] (J.G.); [email protected] (R.M.); [email protected] (U.C.N.); [email protected] (P.K.A.); [email protected] (J.V.R.); [email protected] (Y.S.J.); [email protected] (R.L.T.) 2 Homi Bhaba National Institute, Anushakti Nagar, Mumbai 400 094, India 3 The National Institute of Engineering, Mysuru 570 008, Karnataka, India; [email protected] * Correspondence: [email protected] Received: 30 June 2019; Accepted: 3 October 2019; Published: 5 October 2019 Abstract: The spatial profile of Hα spectrum is regularly measured using a high-resolution multi-track spectrometer in ADITYA tokamak to study the neutral particle behavior. The Monte Carlo neutral particle transport code DEGAS2 is used to model the experimental Hα spectral emissions. Through the modeling of the spectral line profile of Hα, it is found that the neutral hydrogen, which is produced from molecular hydrogen and molecular hydrogen ion dissociation processes contributes 56% to the total Hα emission, and the atoms which are produced from charge-exchange process have 30% contribution. Furthermore, the experimentally measured spatial profile of chord integrated brightness was modeled for the two plasma discharges having relatively high and low density to understand the neutral particle penetration. -
An Application of Survival Analysis to Disruption Prediction Via Random Forests
An application of survival analysis to disruption prediction via Random Forests R.A. Tinguelyy, K.J. Montes, C. Rea, R. Sweeney, and R.S. Granetz Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, MA, USA 02139 Abstract. One of the most pressing challenges facing the fusion community is adequately mitigating or, even better, avoiding disruptions of tokamak plasmas. However, before this can be done, disruptions must first be predicted with sufficient warning time to actuate a response. The established field of survival analysis provides a convenient statistical framework for time-to-event (i.e. time-to-disruption) studies. This paper demonstrates the integration of an existing disruption prediction machine learning algorithm with the Kaplan-Meier estimator of survival probability. Specifically discussed are the implied warning times from binary classification of disruption databases and the interpretation of output signals from Random Forest algorithms trained and tested on these databases. This survival analysis approach is applied to both smooth and noisy test data to highlight important features of the survival and hazard functions. In addition, this method is applied to three Alcator C-Mod plasma discharges and compared to a threshold-based scheme for triggering alarms. In one case, both techniques successfully predict the disruption; although, in another, neither warns of the impending disruption with enough time to mitigate. For the final discharge, the survival analysis approach could avoid the false alarm triggered by the threshold method. Limitations of this analysis and opportunities for future work are also presented. Keywords: tokamak plasma, disruption prediction, survival analysis, machine learning, Random Forest, binary classification 1. -
Evaluation of an Oxygen Transport Coefficient in the Aditya Tokamak
atoms Article Evaluation of an Oxygen Transport Coefficient in the Aditya Tokamak Using the Radial Profile of O4+ Emissivity and the Importance of Atomic Data Used Therein Malay Bikas Chowdhuri 1,* , Joydeep Ghosh 1, Ritu Dey 1, Sharvil Patel 2, Nandini Yadava 3 , Ranjana Manchanda 1, Amrita Bhattacharya 4 , Izumi Murakami 5 and Aditya Team 1 1 Institute for Plasma Research, Bhat 382 428, Gandhinagar, India 2 Birla Institute of Technology-Mesra, Jaipur Campus, Jaipur 302 017, Rajasthan, India 3 The National Institute of Engineering, Mysuru 570 008, Karnataka, India 4 Nuclear Engineering and Technology Programme, Indian Institute of Technology Kanpur, Kanpur 208 016, Uttar Pradesh, India 5 National Institute for Fusion Science, Toki 509-5292, Gifu, Japan * Correspondence: [email protected] Received: 30 June 2019; Accepted: 30 August 2019; Published: 9 September 2019 Abstract: Oxygen impurity transport in the typical discharges of the Aditya tokamak was investigated 3 3 using emissivity radial profile of emissivity of the spectral line (2p3p D3–2p3d F4) at 650.024 nm from the Be-like oxygen ion. This O4+ spectral line was recorded using a 1.0 m multi-track spectrometer capable of simultaneous measurements from eight lines of sight passing through the plasma. The oxygen transport coefficients were determined by reproducing the experimentally measured emissivity profiles of O4+, using a one-dimensional impurity transport code, STRAHL, and photon emissivity coefficient (PEC) belonging to that transition. The PEC values were obtained from both ADAS and NIFS atomic databases. Using both the databases, much higher values of diffusion coefficients compared to the neo-classical values were observed in both high and low magnetic field edge regions of typical Aditya tokamak Ohmic plasma. -
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© -
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. -
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. -
GLAST Science Glossary (PDF)
GLAST SCIENCE GLOSSARY Source: http://glast.sonoma.edu/science/gru/glossary.html Accretion — The process whereby a compact object such as a black hole or neutron star captures matter from a normal star or diffuse cloud. Active galactic nuclei (AGN) — The central region of some galaxies that appears as an extremely luminous point-like source of radiation. They are powered by supermassive black holes accreting nearby matter. Annihilation — The process whereby a particle and its antimatter counterpart interact, converting their mass into energy according to Einstein’s famous formula E = mc2. For example, the annihilation of an electron and positron results in the emission of two gamma-ray photons, each with an energy of 511 keV. Anticoincidence Detector — A system on a gamma-ray observatory that triggers when it detects an incoming charged particle (cosmic ray) so that the telescope will not mistake it for a gamma ray. Antimatter — A form of matter identical to atomic matter, but with the opposite electric charge. Arcminute — One-sixtieth of a degree on the sky. Like latitude and longitude on Earth's surface, we measure positions on the sky in angles. A semicircle that extends up across the sky from the eastern horizon to the western horizon is 180 degrees. One degree, therefore, is not a very big angle. An arcminute is an even smaller angle, 1/60 as large as a degree. The Moon and Sun are each about half a degree across, or about 30 arcminutes. If you take a sharp pencil and hold it at arm's length, then the point of that pencil as seen from your eye is about 3 arcminutes across.