Relevant bibliographies by topics / ITER magnet system

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  1. Journal articles
  2. Dissertations / Theses
  3. Book chapters
  4. Conference papers

Academic literature on the topic 'ITER magnet system'

Author: Grafiati
Published: 4 June 2021
Last updated: 18 February 2022

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Journal articles on the topic "ITER magnet system"

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Huguet, M. "The ITER magnet system." Fusion Engineering and Design 36, no. 1 (April 1997): 23–32. http://dx.doi.org/10.1016/s0920-3796(97)00009-4.

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Mitchell, N., D. Bessette, R. Gallix, C. Jong, J. Knaster, P. Libeyre, C. Sborchia, and F. Simon. "The ITER Magnet System." IEEE Transactions on Applied Superconductivity 18, no. 2 (June 2008): 435–40. http://dx.doi.org/10.1109/tasc.2008.921232.

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Coatanea, M., J. L. Duchateau, P. Hertout, D. Bessette, and F. Rodriguez-Mateos. "Quench Detection in the ITER Magnet System." IEEE Transactions on Applied Superconductivity 20, no. 3 (June 2010): 427–30. http://dx.doi.org/10.1109/tasc.2009.2039705.

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TADA, Eisuke, Kiyoshi YOSHIDA, Kiyoshi SHIBANUMA, Kiyoshi OKUNO, Hiroshi TSUJI, and Susumu SHIMAMOTO. "Reactor Structure and Superconducting Magnet System of ITER." TEION KOGAKU (Journal of Cryogenics and Superconductivity Society of Japan) 28, no. 1 (1993): 2–15. http://dx.doi.org/10.2221/jcsj.28.2.

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Shikov, A., A. Nikulin, A. Silaev, A. Vorobieva, V. Pantsyrnyi, G. Vedernikov, N. Salunin, and S. Sudiev. "Development of the superconductors for ITER magnet system." Journal of Nuclear Materials 258-263 (October 1998): 1929–34. http://dx.doi.org/10.1016/s0022-3115(98)00415-2.

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Okuno, K., D. Bessette, M. Ferrari, M. Huguet, C. Jong, K. Kitamura, Y. Krivchenkov, et al. "Key features of the ITER-FEAT magnet system." Fusion Engineering and Design 58-59 (November 2001): 153–57. http://dx.doi.org/10.1016/s0920-3796(01)00419-7.

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Yoshida, K., Y. Takahashi, and H. Iida. "Control and Instrumentation for the ITER Magnet System." IEEE Transactions on Applied Superconductivity 16, no. 2 (June 2006): 775–78. http://dx.doi.org/10.1109/tasc.2006.873251.

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Thome, Richard J., and ITER Joint Central & Home Teams. "Design & development of the ITER magnet system." Cryogenics 34 (January 1994): 39–46. http://dx.doi.org/10.1016/s0011-2275(05)80008-6.

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Furci, Hernán, and Cesar Luongo. "Simplified thermal model of the ITER magnet system." Cryogenics 63 (September 2014): 241–54. http://dx.doi.org/10.1016/j.cryogenics.2014.02.003.

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Mitchell, Neil, and Arnaud Devred. "The ITER magnet system: configuration and construction status." Fusion Engineering and Design 123 (November 2017): 17–25. http://dx.doi.org/10.1016/j.fusengdes.2017.02.085.

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Dissertations / Theses on the topic "ITER magnet system"

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Di, Sapio Enrico. "Experimental and numerical analyses of ITER Magnet system components." Master's thesis, Alma Mater Studiorum - Università di Bologna, 2019.

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ITER is the international reference project in the development of the nuclear fusion research based on the magnetic confinement. Its purpose is to achieve a stable fusion reaction (it is an experimental reactor). It is not possible for any of the know solid materials to be able to contain this plasma state. Instead, according to Lorentz’s law, a magnetic field can be used: a charged particle in a magnetic field coils around the field lines. The reactor that will allow the magnetic confinement of the plasma is called TOKAMAK. The TOKAMAK is a large toroid-shaped machine composed of various superconducting magnet system: Toroidal Field Coil (TF), Poloidal Field (PF) coil, Central Solenoid (CS) and Correction Coil (CC). The use of this complex system of superconducting magnets is a consequence of the high magnetic field necessary for the confinement of the plasma (superconductors are the only way to build magnets with a large confinement field). The construction of this important project is currently underway in Cadarache in the south of France. It is expected that the deuterium and tritium fusion experiments will start only from 2035, and from 2037 the plant will begin the shutdown phase of the expected duration of 5 years. This thesis summarizes the work done during the six months spent at ITER Organization in France. The first chapter has been based on the analyses of superconducting joints with a specific focus into post-processing AC loss energy for all TF joint SULTAN samples. The purpose of the chapter is to summarize the AC loss characterization of TF Joint SULTAN samples, a TF-TF Joint SULTAN sample. The analysis focused on TFJEU12 SULTAN sample to present the post-processing procedure and give a summary overview of all samples. The second chapter has been based on an analytical study of the Correction Coil Supports. The purpose of this work is to present a thermal and energy model of the CCs.
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Coatanea-gouachet, Marc. "Quench detection and behaviour in case of quench in the ITER magnet systems." Thesis, Aix-Marseille, 2012. http://www.theses.fr/2012AIXM4739/document.

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Le quench d'un système magnétique d'ITER est une transition irréversible d'un conducteur, de l'état supraconducteur à l'état normal résistif. Cette zone normale se propage le long du câble au cours du temps, en dissipant une grande quantité d'énergie. La détection se doit d'être suffisamment rapide afin de permettre une décharge de l'énergie magnétique et éviter un endommagement permanent du système. La détection primaire de quench d'ITER est basée sur la détection de la tension due au quench, qui est le moyen le plus rapide. L'environnement magnétique perturbé pendant le scenario plasma rend la détection de cette tension très difficile, à cause des hautes tensions inductives qu'il génère dans les bobinages. En conséquence, des compensations de tension sont nécessaires afin de discriminer la tension résistive due au quench.Une solution conceptuelle de la détection de quench basée sur la mesure des tensions est proposée pour les trois grands systèmes magnétiques d'ITER. Pour ceci, une méthodologie claire est développée, incluant le calcul classique selon le critère du point chaud, l'étude de la propagation de quench grâce au code commercial Gandalf, et l'estimation des perturbations inductives, grâce au développement du code TrapsAV. Des solutions adaptées sont proposée pour ces systèmes ainsi que les paramètres de cette détection, qui sont le seuil de détection (entre 0.1 V et 0.55 V) et le temps de discrimination (entre 1 s et 1.2 s). Les valeurs choisies, et en particulier le temps de discrimination, sont suffisamment élevées pour garantir la fiabilité du système, et pour éviter le déclenchement intempestif de décharges rapides non nécessaires
The quench of one of the ITER magnet system is an irreversible transition from superconducting to normal resistive state, of a conductor. This normal zone propagates along the cable in conduit conductor dissipating a large power. The detection has to be fast enough to dump out the magnetic energy and avoid irreversible damage of the systems. The primary quench detection in ITER is based on voltage detection which is the most rapid detection. The very magnetically disturbed environment during the plasma scenario, makes the voltage detection particularly difficult, inducing large inductive components in the coils and voltage compensations have to be designed to discriminate the resistive voltage associated with the quench. A conceptual design of the quench detection based on voltage measurements is proposed for the three majors magnet systems of ITER. For this, a clear methodology was developed. It includes the classical hot spot criterion, the quench propagation study using the commercial code Gandalf and the careful estimation of the inductive disturbances by developing the TrapsAV code.Specific solutions have been proposed for the compensation in the three ITER magnet systems and for the quench detection parameters which are the voltage threshold (in the range of 0.1 V- 0.55 V) and the holding time (in the range of 1 -1.4 s). The selected values, in particular the holding time, are sufficiently high to ensure the reliability of the system and avoid fast safety discharges not induced by a quench which is a classical problem
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Book chapters on the topic "ITER magnet system"

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Yoshida, K., V. Kalinin, S. Stoner, and T. Kato. "Requirements and Interfaces to Cryogenic and Power Supply Plants for the ITER Magnet System." In A Cryogenic Engineering Conference Publication, 701–8. Boston, MA: Springer US, 1996. http://dx.doi.org/10.1007/978-1-4613-0373-2_91.

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Tugarinov, S., M. von Hellermann, I. Beigman, V. Dokouka, R. Khayrutdinov, A. Krasilnikov, A. Malaquias, I. Tolstikhina, and L. Vainshtein. "Conceptual Design of the Cxrs System for Iter-Feat." In Advanced Diagnostics for Magnetic and Inertial Fusion, 253–56. Boston, MA: Springer US, 2002. http://dx.doi.org/10.1007/978-1-4419-8696-2_46.

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Huguet, M. "The ITER magnet system." In Fusion Technology 1996, 23–32. Elsevier, 1997. http://dx.doi.org/10.1016/b978-0-444-82762-3.50008-2.

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Mitchell, N., L. Bottura, and S. Chiocchio. "SAFETY ANALYSIS OF THE MAGNET SYSTEM FOR NET AND ITER." In Fusion Technology 1992, 1739–43. Elsevier, 1993. http://dx.doi.org/10.1016/b978-0-444-89995-8.50341-6.

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Rigoutsos, Isidore, and Daniel Platt. "Representation and Matching of Small Flexible Molecules in Large Databases of 3D Molecular Information." In Pattern Discovery in Biomolecular Data. Oxford University Press, 1999. http://dx.doi.org/10.1093/oso/9780195119404.003.0013.

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In recent years, the need to process and mine available information repositories has been increasing. The variety of the data contained in the targeted databases has given rise to a variety of tools for mining them, and computers have assumed an increasingly important role in this process. One of the many domains in which this scenario has been repeated is that of the drug discovery and design process. Computers have helped researchers to quickly eliminate unlikely drug candidates, to home in on promising ones, and to shorten the lead-compound-search cycle. Researchers are helped in this multidisciplinary effort by accessing proprietary and public resources containing crystallography, nuclear magnetic resonance, toxicology, pharmacology, and other types of data. Using the computer to filter out unlikely candidates can greatly shorten the length of a cycle in this iterative process. Some scenarios encountered in the context of the drug design process include . . . (a) a pharmacophore model that has been proposed from several active molecules—one wishes to determine other molecules that either corroborate or refute the model; (b) a set of untested molecules that exhibit biological activity—one wishes to identify relationships between their 3D structure and the activity; (c) a ligand that has been proposed to be active in a certain conformation- -other molecules that mimic the ligand’s behavior are sought. . . . The common element in all of these cases is that they are in essence searches for member elements in one or more repositories, each of the elements having some desired properties or behavior. Let us take a step back and reexamine the problem we are trying to solve. Two basic elements of the problem are “representation” and “storage.” If answers to both of these questions are available, then one can implement a retrieval system the properties and behavior of which are directly related to those of the two basic elements. We begin with a body of knowledge D that consists of D data items {di / i = 1,..., D}. Each data item is represented by a set of k properties and their respective values.
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Conference papers on the topic "ITER magnet system"

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Sborchia, C., E. Barbero Soto, R. Batista, B. Bellesia, A. Bonito Oliva, E. Boter Rebollo, T. Boutboul, et al. "Overview of ITER magnet system and European contribution." In 2011 IEEE 24th Symposium on Fusion Engineering (SOFE). IEEE, 2011. http://dx.doi.org/10.1109/sofe.2011.6052218.

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Gallix, R., Y. Fu, C. Jong, P. Y. Lee, B. L. Hou, and G. D. Jian. "Updated design of the ITER magnet system gravity supports." In 2009 23rd IEEE/NPSS Symposium on Fusion Engineering - SOFE. IEEE, 2009. http://dx.doi.org/10.1109/fusion.2009.5226496.

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Nakajima, H., K. Hamada, K. Okuno, K. Hada, and E. Tada. "New Cryogenic Steels and Design Approach for ITER Superconducting Magnet System." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22674.

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A new design code has been developed for construction and operation/maintenance of the International Thermonuclear Experimental Reactor (ITER). A superconducting magnet system is one of the key components of ITER and its design code includes new cryogenic materials and design approach with taking account of unique features of a performance of the superconducting magnet. The new materials are nitrogen strengthened austenitic stainless steels, which have a yield strength (Sy) of over 1000 MPa and fracture toughness (KIc) of over 200 MP√m at liquid helium temperature (4K). The feature of the design approach is use of the allowable stress defined by only 2/3 Sy measured at 4K. A concept and reliability of the new design approach using new cryogenic materials for the ITER superconducting magnet system are discussed in this paper.
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Okuno, Kiyoshi, Hideo Nakajima, Yoshikazu Takahashi, and Norikiyo Koizumi. "Progress in ITER Project and Its Superconducting Magnet System in Japan." In ASME 2009 Pressure Vessels and Piping Conference. ASMEDC, 2009. http://dx.doi.org/10.1115/pvp2009-77478.

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The ITER Agreement was signed on 21 November 2006 and the ITER Organization (IO) was officially started. IO undertook a Design Review of ITER and the ITER baseline design was established as a basis for starting construction, together with the reference Integrated Project Schedule. In parallel, Japan Atomic Energy Agency (JAEA) performed extensive development work as procurement preparation including TF conductor, TF coil winding and TF coil structures. Based on the achievements from these developments, JAEA started the actual procurement from March 2008 by placing contracts on the industries in line with the Integrated Project Schedule.
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Wu, Shuqin, Yuntao Song, Chao Xing, and Delong Luo. "The Status on Design Collaboration in ITER Chinese Domestic Agency." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-15159.

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Being an international cooperative engineering project, integration and compatibility of ITER design from numbers of different contributors worldwide is one of the crucial challenges. In order to fully integrate analysis, design, integration, and simulation of mechanical and plant design, and minimize interfaces between tools and methodologies, ITER Project developed a Computer Assisted Design (CAD) collaborative Platform for ITER Organization (IO) and all the parties to implement design collaborations. And also, ITER project standardized design activity via mandatory rules and recommendations for the design lifecycle and tool selections which are documented in the CAD Manual and other related supporting satellite documents. ITER Chinese Domestic Agency (CN DA) as one of seven parties of ITER Project, undertakes twelve Procurement Packages to design and manufacture several ITER TOKAMAK Machine components and systems, including Magnet Support, Corrective Coils, Magnet Feeders, AC/DC Converters, Diagnostic Systems, Gas Injection System, Glow Discharge Cleaning and so on. Most of them comprise plenty of design work with different design maturities.CN DA accepts ITER design rules and standards, and performs proper deign collaboration schemes according to corresponding PA Design Collaboration Implementation Forms (DCIF). This paper will present the status of CN DA design collaboration with IO and other DAs. It will include an overall description of design collaboration strategy and infrastructure in CN DA; the introduction of design tasks CN DA involved; and the associated organization and implementation of design collaboration schemes in specific PAs.
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Huang, Chuanjun, Rongjin Huang, and Laifeng Li. "Mechanical property tests on structural materials for ITER magnet system at low temperatures in China." In ADVANCES IN CRYOGENIC ENGINEERING: Transactions of the International Cryogenic Materials Conference ICMC Volume 60. AIP Publishing LLC, 2014. http://dx.doi.org/10.1063/1.4860647.

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Chung, Yoon Do, Jiseong Kim, Kwang Myung Park, and Eun Young Park. "Conceptual Design of Quench Detection System for High Field ITER Magnet using Wireless Power Transfer Technology." In 2019 Joint International Symposium on Electromagnetic Compatibility, Sapporo and Asia-Pacific International Symposium on Electromagnetic Compatibility (EMC Sapporo/APEMC). IEEE, 2019. http://dx.doi.org/10.23919/emctokyo.2019.8893670.

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Suzuki, Tetsuya, Arata Nishimura, and Hideo Nakajima. "JSME Construction Standard for Superconducting Magnet of Fusion Facility ”Quality Assurance”." In ASME 2009 Pressure Vessels and Piping Conference. ASMEDC, 2009. http://dx.doi.org/10.1115/pvp2009-77337.

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This standard was developed to be applied the superconducting magnet structure of ITER, Tokamak type fusion facility. The standard for the conformity assessment and quality assurance was decided as a subsection of the standard, to ensure the quality of the superconducting magnet structure for fusion energy. Conformity assessment is indispensable as well as quality assurance for the products to perform their function satisfactorily. Most of Japanese voluntary consensus standards in nuclear field limited their contents to technical requirements only, so conformity assessment has been performed by regulatory authority. Ensuring conformance to the standard is necessary to satisfy Japanese responsibility for in-kind contribution to ITER. For this purpose, fundamental requirements for conformity assessment were defined. Role and responsibility of Owner, Manufacturer, Installer, Qualified Inspector, Standard-Expert Engineer were defined. The requirements of certification for Design Specification, Design Report, Fabrication Specification, Installation Specification, Data Report were defined as well. In conformity assessment, realistic Qualified Inspection and Design Certification were pursued, considering the legislation, infrastructure and prospective user of standard in Japan. These procedures of certification and qualified inspection specific to national system were separated from main body as appendix for international user to adopt their own alternative system. The quality assurance requirements consists of 18 articles, such as organization, quality assurance program, design control, document control etc. were used. Each article was designed to constitute simplified performance based requirement. In addition, guidance was given in non-mandatory appendix for the users to apply performance-based requirements effectively.
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Chida, Yutaka, Masahide Iguchi, Hideo Nakajima, Koichi Oosemochi, Kenichiro Niimi, and Daisuke Tokai. "Validation of Fabricability for ITER TF Coil Structures." In ASME 2011 Pressure Vessels and Piping Conference. ASMEDC, 2011. http://dx.doi.org/10.1115/pvp2011-57284.

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The ITER superconducting magnet system consists of 18 Troidal Field (TF) coils, 6 Central Solenoid (CS) modules, 6 Poloidal Field (PF) coils and 18 Correction coils. The Japan Atomic Energy Agency (JAEA), acting as the Japan Domestic Energy Agency (JADA) in the ITER project, is responsible for the procurement of 9 TF coil winding packs (WP), structures for 19 TF coils, (including one spare), and assembly of the WP and the coil structures for 9TF coils [1]. TF coil structures, which support large electromagnetic force generated in TF coils under the cryogenic temperature (about 4K), are the mega welding structures composed of coil case and support structures made of heavy thickness high strength and high toughness stainless steel. JAEA started the study on welding trials for the materials to be used since 2008 and have been demonstrating of full scale mock-up model fabrication for main sub-components since 2010. This paper introduces the results on welding trials and status of full scale mock-up model fabrication before fabricating actual products. Enough weld joint performance was obtained with the base metal of JJ1 (FMJJ1 specified by JSME (The Japan Society of Mechanical Engineers) Code [2] and is developed in Japan) and SS316LN (FM316LN specified by JSME Code), and also their combination using JJ1 filler wire (FMYJJ1 specified by JSME Code and is developed in Japan) by narrow gap GTAW process. Welding deformation such as angular distortion between outer plate and side plates of U-shape segment could be controlled and minimized by using effective restraint jig in trial manufacturing of 1m long leg. Validity of welding technology and manufacturing design are confirmed during full scale mock-up model fabrication. And also investigations such as UT (ultrasonic test) and effective welding process for rationalization have been performed.
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Shikov, A. K., V. I. Pantsyrny, N. I. Kozlenkova, R. M. Vasilyev, A. E. Vorobieva, K. A. Mareev, S. V. Sudijev, and U. (Balu) Balachandran. "A STUDY ON CORRELATION BETWEEN J[sub c](4.2 K) AND CURRENT SHARING TEMPERATURE T[sub cs] OF Nb[sub 3]Sn STRANDS AND SHORT SAMPLE OF CONDUCTOR FOR TOROIDAL FIELD COILS OF ITER MAGNET SYSTEM." In TRANSACTIONS OF THE INTERNATIONAL CRYOGENIC MATERIALS CONFERENCE—ICMC: Advances in Cryogenic Engineering Materials. AIP, 2010. http://dx.doi.org/10.1063/1.3402306.

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