Relevant bibliographies by topics / Fusion magnet

Academic literature on the topic 'Fusion magnet'

Author: Grafiati
Published: 14 March 2023

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Journal articles on the topic "Fusion magnet"

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WEBER, HARALD W. "RADIATION EFFECTS ON SUPERCONDUCTING FUSION MAGNET COMPONENTS." International Journal of Modern Physics E 20, no. 06 (June 2011): 1325–78. http://dx.doi.org/10.1142/s0218301311018526.

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Nuclear fusion devices based on the magnetic confinement principle heavily rely on the existence and performance of superconducting magnets and have always significantly contributed to advancing superconductor and magnet technology to their limits. In view of the presently ongoing construction of the tokamak device ITER and the stellerator device Wendelstein 7X and their record breaking parameters concerning size, complexity of design, stored energy, amperage, mechanical and magnetic forces, critical current densities and stability requirements, it is deemed timely to review another critical parameter that is practically unique to these devices, namely the radiation response of all magnet components to the lifetime fluence of fast neutrons and gamma rays produced by the fusion reactions of deuterium and tritium. I will review these radiation effects in turn for the currently employed standard "technical" low temperature superconductors NbTi and Nb 3 Sn , the stabilizing material ( Cu ) as well as the magnet insulation materials and conclude by discussing the potential of high temperature superconducting materials for future generations of fusion devices, such as DEMO.
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Bonin, Mélodie, Frédéric-Georges Fontaine, and Dominic Larivière. "Comparative Studies of Digestion Techniques for the Dissolution of Neodymium-Based Magnets." Metals 11, no. 8 (July 21, 2021): 1149. http://dx.doi.org/10.3390/met11081149.

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The digestion of neodymium (NdFeB) magnets was investigated in the context of recycling rare earth elements (i.e., Nd, Pr, Dy, and Tb). Among more conventional digestion techniques (microwave digestion, open vessel digestion, and alkaline fusion), focused infrared digestion (FID) was tested as a possible approach to rapidly and efficiently solubilize NdFeB magnets. FID parameters were initially optimized with unmagnetized magnet powder and subsequently used on magnet pieces, demonstrating that the demagnetization and grinding steps are optional.
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Menard, J. E. "Compact steady-state tokamak performance dependence on magnet and core physics limits." Philosophical Transactions of the Royal Society A: Mathematical, Physical and Engineering Sciences 377, no. 2141 (February 4, 2019): 20170440. http://dx.doi.org/10.1098/rsta.2017.0440.

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Compact tokamak fusion reactors using advanced high-temperature superconducting magnets for the toroidal field coils have received considerable recent attention due to the promise of more compact devices and more economical fusion energy development. Facilities with combined fusion nuclear science and Pilot Plant missions to provide both the nuclear environment needed to develop fusion materials and components while also potentially achieving sufficient fusion performance to generate modest net electrical power are considered. The performance of the tokamak fusion system is assessed using a range of core physics and toroidal field magnet performance constraints to better understand which parameters most strongly influence the achievable fusion performance. This article is part of a discussion meeting issue ‘Fusion energy using tokamaks: can development be accelerated?’.
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Goll, Dagmar, Felix Trauter, Ralf Loeffler, Thomas Gross, and Gerhard Schneider. "Additive Manufacturing of Textured FePrCuB Permanent Magnets." Micromachines 12, no. 9 (August 31, 2021): 1056. http://dx.doi.org/10.3390/mi12091056.

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Permanent magnets based on FePrCuB were realized on a laboratory scale through additive manufacturing (laser powder bed fusion, L-PBF) and book mold casting (reference). A well-adjusted two-stage heat treatment of the as-cast/as-printed FePrCuB alloys produces hard magnetic properties without the need for subsequent powder metallurgical processing. This resulted in a coercivity of 0.67 T, remanence of 0.67 T and maximum energy density of 69.8 kJ/m3 for the printed parts. While the annealed book-mold-cast FePrCuB alloys are easy-plane permanent magnets (BMC magnet), the printed magnets are characterized by a distinct, predominantly directional microstructure that originated from the AM process and was further refined during heat treatment. Due to the higher degree of texturing, the L-PBF magnet has a 26% higher remanence compared to the identically annealed BMC magnet of the same composition.
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Shimamoto, Susumu, and Takashi Satow. "Superconducting Magnet Development for Fusion Reactor." IEEJ Transactions on Power and Energy 119, no. 11 (1999): 1143–45. http://dx.doi.org/10.1541/ieejpes1990.119.11_1143.

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Miya, Kenzo. "Super conducting magnet technologies for fusion reactor." Kakuyūgō kenkyū 56, no. 2 (1986): 105–14. http://dx.doi.org/10.1585/jspf1958.56.105.

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Okuno, K., A. Shikov, and N. Koizumi. "Superconducting magnet system in a fusion reactor." Journal of Nuclear Materials 329-333 (August 2004): 141–47. http://dx.doi.org/10.1016/j.jnucmat.2004.04.151.

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Sawan, Mohamed E., and Peter L. Walstrom. "Superconducting Magnet Radiation Effects in Fusion Reactors." Fusion Technology 10, no. 3P2A (November 1986): 741–46. http://dx.doi.org/10.13182/fst86-a24829.

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Shimamoto, S. "Superconducting magnet development for fusion at JAERI." Cryogenics 25, no. 4 (April 1985): 171–77. http://dx.doi.org/10.1016/0011-2275(85)90132-8.

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HAMADA, Kazuya, and Norikiyo KOIZUMI. "Electromagnetic Phenomenon in Superconducting Magnet for Fusion Facility. Forced Flow Superconducting Magnet." Journal of Plasma and Fusion Research 78, no. 7 (2002): 616–24. http://dx.doi.org/10.1585/jspf.78.616.

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Dissertations / Theses on the topic "Fusion magnet"

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KHOLIA, AKSHAT. "Thermal Hydraulic numerical analysis of Fusion superconducting magnet systems." Doctoral thesis, Politecnico di Torino, 2013. http://hdl.handle.net/11583/2507886.

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In the present scenario, the International Thermonuclear Experimental Reactor (ITER) is in progress and efforts are being made to extend ITER to DEMOnstration Power plant (DEMO) with the purpose to harness the fusion energy for peaceful and constructive purposes. ITER uses the sueperconducting magnet systems for trapping and maneuvering plasma inside the giant tokamak machines. Superconductivity only entails under the critical conditions of temperature, magnetic field and current density. If any of these parameters surpass the critical value, the quench ensues in the cable. In the real system scenarios, electromagnetic, radiative & conductive loads are present, which may affect the performance of the machine. The magnet designer can change the parameters in terms of current and magnetic field to ensure that the critical conditions are met, but when it comes to temperature, it is really hard to locate the hot spot locations. To envisage such situations, it is essential to study thermal hydraulics and hence system code is needed for the whole superconducting magnet system. For such purposes, Cryogenic Circuit, Conductor and Coil code (4C) was built, imbibing the thermal hydraulic modeling of the cable in Conduit conductors (including strands) coupled with structures (which give support to the winding pack, wound by conductors) and an external cryogenic circuit. During the thesis work, the pre-existing 4C code, was modeled for various coils with or without external cooling circuit as required. Henceforth, it was implemented against the wide range of transients, fast transients (~ few seconds) as well as slow transients (~ few days or weeks) to test the flexibility of the code in studying the wide range of physical phenomenon on different time scales. Eventually, the results were validated against the available experimental data to observe the precision of the model in 4C code. One of the analysis carried out during this dissertation included the cool down of one of the non planar coils (NPC) used in Wendelstein 7-X, which was an example of slow transient. In the domain of fast transients, an extensive analysis of AC losses in one of poloidal field (PF) coils with an external cooling circuit, was performed for Korean Superconducting Tokamak Advanced Research (KSTAR), functional fusion device.
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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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ZAPPATORE, ANDREA. "Modelling Innovative High Temperature Superconductors for Fusion Applications." Doctoral thesis, Politecnico di Torino, 2021. http://hdl.handle.net/11583/2935600.

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Barber, Julien (Julien Victor). "Investigation of cryogenic cooling for a high-field toroidal field magnet used in the SPARC fusion reactor design." Thesis, Massachusetts Institute of Technology, 2018. http://hdl.handle.net/1721.1/118738.

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Thesis: S.M., Massachusetts Institute of Technology, Department of Mechanical Engineering, 2018.
Cataloged from PDF version of thesis.
Includes bibliographical references (pages 111-114).
Rare Earth Barium Copper Oxide (REBCO) High Temperature Superconducting (HTS) tapes are being considered for the Toroidal Field (TF) magnets of the highly compact, high-field SPARC Version 0 (V0) reactor design. The V0 design is set to operate at magnetic fields as high as 20 T, and operating temperatures ranging from 10-30 K. Due to the increase in range of operating conditions made available through the HTS-based magnets, a new set of cryogenic fluids are being considered for forced flow cooling. This thesis analyzes the thermophysical properties of helium, hydrogen, and neon, and constructs a numerical model to investigate the forced flow cooling for REBCO HTS tapes under the extreme heating conditions present in the SPARC V0 design. Four design criteria are used to assess each cryogen, including the current sharing temperature, fluid inlet temperature, cable pressure drop ([delta]P), and operating pressure. From the results of the model, neon is removed from consideration due to its high required pressure drop and low temperature margins imposed by the superconductor current sharing limit. Hydrogen provides the highest effective heat transfer rate operating at inlet conditions of 1.5 MPa and 15 K, but is constrained by safety considerations. Helium is also able to meet the current sharing condition, but with higher initial pressure and lower initial temperature. Using the numerical model, an analysis using the four design criteria finds an optimal operating condition for helium of 2.5 MPa and 10 K based on minimizing cable pressure drop ([delta]P) and inlet pressure, while maximizing the fluid's inlet temperature. With a target operating point defined, an experimental cryogenic flow loop is designed with the purpose of verifying the high heat transfer rates required for the high-pressure, supercritical helium flow in the SPARC reactor. The flow loop uses a pressure differential to drive flow at a target mass flow rate of 46 g/s. To simulate a plasma pulse, the fluid flow is subject to heat fluxes up to 45 kW/m² for a minimum duration of ten seconds.
Supported by the U.S. Department of Energy, Office of Fusion Energy Science Grant: DE-FC02-93ER54186
by Julien Barber.
S.M.
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Dehnen, Matthias [Verfasser]. "Degenerative Veränderungen des angrenzenden Segments nach anteriorer zervikaler Diskektomie und Fusion : eine Magnet Resonanz Untersuchung im Langzeitverlauf / Matthias Dehnen." Saarbrücken : Saarländische Universitäts- und Landesbibliothek, 2020. http://d-nb.info/1214240763/34.

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Bayer, Christoph M. [Verfasser]. "Characterization of High Temperature Superconductor Cables for Magnet Toroidal Field Coils of the DEMO Fusion Power Plant / Christoph M. Bayer." Karlsruhe : KIT Scientific Publishing, 2017. http://www.ksp.kit.edu.

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Talami, Matteo. "Modeling of the Toroidal Field Insert coil for the ITER Project." Master's thesis, Alma Mater Studiorum - Università di Bologna, 2017. http://amslaurea.unibo.it/12916/.

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Il contenuto della tesi riguarda le analisi numeriche e sperimentali effettuate su un campione di cavo superconduttivo del sistema magnetico del reattore sperimentale per la fusione nucleare “ITER”. In particolare, il campione di cavo denominato “Toroidal Field Insert” o “TFI”, appartiene al sistema magnetico toroidale della macchina e viene inserito in un solenoide esterno in modo da replicare le condizioni di campo magnetico tipiche del normale funzionamento di questo conduttore. Le analisi sperimentali effettuate sul campione sono mirate alla caratterizzazione del comportamento durante un ipotetico ciclo di vita del cavo. I parametri principalmente studiati risultano essere: la caratterizzazione dello stato superconduttivo prima e dopo le varie sollecitazioni imposte, l’efficacia idraulica del raffreddamento e la stabilità termica del magnete. In modo complementare alla analisi dei dati sperimentali, due modelli numerici a diverse scale sono stati sviluppati e testati: un primo modello, alla scala di sistema, si occupa dello studio termico e idraulico dell’intera porzione di cavo testata; il secondo, alla scala di componente, si occupa della simulazione elettromagnetica di un riscaldatore induttivo installato sul conduttore volto a misurarne la stabilità. Il confronto tra l’analisi numerica e quella sperimentale ha permesso la comprensione dei principali fenomeni in gioco e la caratterizzazione del conduttore testato.
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Lopes, Carmelo Riccardo. "Design and Simulation of Fast Discharge Units (FDUs) for Toroidal Field Coils of Divertor Tokamak Test (DTT)." Doctoral thesis, Università degli Studi di Palermo, 2023. https://hdl.handle.net/10447/580087.

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Questa tesi riassume il lavoro svolto durante il triennio di dottorato nel periodo compreso tra il 2019 e il 2022. Come è ben noto nella comunità scientifica, l'ambiziosissimo progetto di fusione nucleare ha richiesto e richiede notevoli risorse ed investimenti; La tabella di marcia per la generazione di energia da fusione nucleare su larga scala comprende missioni impegnative. I progetti ITER e DEMO, essendo progetti internazionali, richiedono la collaborazione (sia dal punto di vista economico che tecnico) di diversi Paesi a livello europeo ed extraeuropeo; per questo motivo i vari aspetti tecnologici, che verranno poi implementati e applicati nei reattori a fusione finali, vengono prima analizzati, simulati e gestiti da vari enti degli stati membri del progetto (compresa l'Italia). Una delle strutture di ricerca più importanti per questi progetti si trova presso la sede ENEA di Frascati (RM) ed è denominata DTT (divertor tokamak test facility). La struttura DTT è progettata per esplorare tutte le linee di regimi operativi del plasma rilevanti per ITER e DEMO; In particolare sarà possibile dimostrare la fattibilità fisica e tecnologica di varie configurazioni di divertore. In questo modo sarà possibile integrare le conoscenze su concetti di divertori alternativi già sperimentati su macchine esistenti. Poiché l'energia magnetica immagazzinata nei magneti superconduttori è dell'ordine di 2GJ-4GJ (per DTT), in caso di guasto o quench deve esserci la possibilità di estrarla molto velocemente per salvaguardare l'integrità del Tokamak e dei superconduttori. In questo caso intervengono i cosiddetti sistemi FDU (Fast Discharge Unit), costituiti essenzialmente da resistenze per consentire la scarica e la rapida dissipazione dell'energia. La protezione viene realizzata collegando una resistenza di scarica in serie ad ogni blocco di magneti suddivisi in vari gruppi a seconda della loro configurazione elettrica. L'obiettivo principale di questa tesi è quindi quello di riportare tutti i modelli, le simulazioni ei risultati elaborati per l'intera durata del corso di studio nell'ambito dello sviluppo di Fast Discharge Units (FDU).
This thesis summarizes the work carried out during the 3-year PhD course in the period between 2019 and 2022. As is well known in the scientific community, the very ambitious nuclear fusion project has required and still requires considerable resources and investments; The roadmap for large-scale nuclear fusion power generation is comprised of challenging missions. The ITER and DEMO projects, being international projects, require the collaboration (both from an economic and technical point of view) of different countries at European and non-European level; for this reason, the various technological aspects, which will then be implemented and applied in the final fusion reactors, are first analyzed, simulated, and managed by various bodies of the project member states (including Italy). One of the most important research facilities for these projects is located at the ENEA headquarters in Frascati (RM) and is called DTT (divertor tokamak test facility). The DTT structure is designed to explore all lines of plasma operating regimes relevant to ITER and DEMO; In particular, it will be possible to demonstrate the physical and technological feasibility of various divertor configurations. In this way it will be possible to integrate knowledge on alternative divertor concepts already tested on existing machines. Since the magnetic energy stored in superconducting magnets is of the order of 2GJ-4GJ (for DTT), in the event of a failure or quench there must be the possibility to extract it very quickly to safeguard the integrity of the Tokamak and superconductors. In this case, the so-called FDU systems (fast discharge unit) intervene, which basically consist of resistors to allow discharge and fast dissipation of energy. Protection is carried out by connecting a discharge resistor in series to each block of magnets divided into various groups depending on their electrical configuration. The main objective of this thesis so is to report all the models, simulations and results processed for the entire duration of the course of study as part of the development of Fast Discharge Units (FDU).
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Hasnain, Bakhtiyar Asef, and Ademir Hodzic. "Design and Simulation of a Slotless Aircored PM Synchronous Generator." Thesis, Uppsala universitet, Institutionen för elektroteknik, 2020. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-425268.

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This thesis is a study on an unconventional slow speed direct drive permanent magnet (PM) generator. Unlike a standard permanent magnet synchronous generator (PMSG) which has the copper coils wound around iron teeth, the work in this thesis will present a generator where the copper coils are directly mounted on the stator which eliminates the slots and teeth in the generator. By having a slotless design it is possible to eliminate cogging torque, iron losses in teeth and achieve a lightweight design. These characteristics can prove useful when developing generators for an application such as wind turbines, or more specifically vertical axis wind turbines (VAWTs) in remote areas where weight and serviceability is of concern. This thesis consists of two main parts where the main focus was on the design and simulation of slotless generators. The second part of the thesis was to investigate an available slotless axial flux machine. For the simulations, three different models were created in 2D using CAD software. Two of the models were double-rotor slotless generators and one was a single rotor variant. The electromagnetic properties of these models were analysed using FEMM and COMSOL. The results showed that the double rotor variant with the smaller magnets were more favourable considering the price of magnets and no iron core losses. The experimental results of the axial flux machine gave insight into the construction of commercially available axial slotless generators which could be used to further analyse these types of machines.
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Bruzzone, Pierluigi. "AC losses in high current superconductors for nuclear fusion magnets /." [S.l.] : [s.n.], 1987. http://e-collection.ethbib.ethz.ch/show?type=diss&nr=8224.

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Books on the topic "Fusion magnet"

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Kulsrud, R. M. Lectures on topics in magnetic reconnection and transport in fusion devices. Nagoya, Japan: Institute of Plasma Physics, Nagoya University, 1986.

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1949-, Yamazaki K., ed. Design scalings and optimizations for super-conducting large helical devices. Nagoya, Japan: National Institute for Fusion Science, 1990.

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United States. National Aeronautics and Space Administration., ed. Investigation of the possibility of using nuclear magnetic spin alignment: Final report. [Huntsville, Ala.]: DIR, Inc., 1998.

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Gurūpu, Kakuyūgō Kagaku Kenkyūjo Ōgata Herikaru Sōchi Sekkei. Ōgata herikaru sōchi keikaku. [Tokyo]: Monbushō Kakuyūgō Kagaku Kenkyūjo Ōgata Herikaru Sōchi Sekkei Gurūpu, 1990.

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A, Iiyoshi, ed. Design study of the large helical device. Nagoya, Japan: National Institute for Fusion Science, 1990.

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Kakuyūgō Kagaku Kenkyūjo. NIFS Kakuyūgō Kōgaku Kenkyū Purojekuto FFHR Sekkei Gurūpu. Herikaru-gata kakuyūgōro FFHR-d1 gainen sekkei chūkan hōkokusho. Toki-shi: Kakuyūgō Kagaku Kenkyūjo, 2013.

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Dolan, Thomas J., Ralph W. Moir, Wallace Manheimer, Lee C. Cadwallader, and Martin J. Neumann. Magnetic Fusion Technology. Springer, 2014.

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Dolan, Thomas J. Magnetic Fusion Technology. Springer, 2016.

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Dolan, Thomas J. Magnetic Fusion Technology. Springer, 2014.

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Raum, Elizabeth. What's the Attraction? (Raintree Fusion: Magnetism). Raintree, 2006.

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Book chapters on the topic "Fusion magnet"

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Shimamoto, S. "Development of Superconducting Magnet for Fusion Power." In Advances in Superconductivity, 43–49. Tokyo: Springer Japan, 1989. http://dx.doi.org/10.1007/978-4-431-68084-0_6.

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Fietz, William A. "Experience in the Operation of the International Fusion Superconducting Magnet Test Facility." In Advances in Cryogenic Engineering, 517–28. Boston, MA: Springer US, 1990. http://dx.doi.org/10.1007/978-1-4613-0639-9_61.

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Gori, Roberto E., and Pierluigi Zaccaria. "Plastic Bending Large Displacement Analysis and Spring-Back of a Conductor Jacket of a Superconducting Magnet for Fusion Reactors." In 11th International Conference on Magnet Technology (MT-11), 674–79. Dordrecht: Springer Netherlands, 1990. http://dx.doi.org/10.1007/978-94-009-0769-0_116.

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Humer, K., P. Rosenkranz, H. W. Weber, J. A. Rice, and C. S. Hazelton. "Mechanical Strength, Swelling and Weight Loss of Inorganic Fusion Magnet Insulation Systems Following Reactor Irradiation." In Advances in Cryogenic Engineering Materials, 135–41. Boston, MA: Springer US, 2000. http://dx.doi.org/10.1007/978-1-4615-4293-3_17.

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Dolan, Thomas J., and Denis P. Ivanov. "Superconducting Magnets." In Magnetic Fusion Technology, 119–74. London: Springer London, 2013. http://dx.doi.org/10.1007/978-1-4471-5556-0_4.

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Dolan, Thomas J. "Pulsed and Water-Cooled Magnets." In Magnetic Fusion Technology, 71–118. London: Springer London, 2013. http://dx.doi.org/10.1007/978-1-4471-5556-0_3.

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Dolan, Thomas J., and Alexander Parrish. "Introduction." In Magnetic Fusion Technology, 1–44. London: Springer London, 2013. http://dx.doi.org/10.1007/978-1-4471-5556-0_1.

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Dolan, Thomas J. "Cryogenic Systems." In Magnetic Fusion Technology, 491–511. London: Springer London, 2013. http://dx.doi.org/10.1007/978-1-4471-5556-0_10.

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Dolan, Thomas J., Alan E. Costley, and Jana Brotankova. "Plasma Diagnostics." In Magnetic Fusion Technology, 513–617. London: Springer London, 2013. http://dx.doi.org/10.1007/978-1-4471-5556-0_11.

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Dolan, Thomas J., and Lee C. Cadwallader. "Safety and Environment." In Magnetic Fusion Technology, 619–52. London: Springer London, 2013. http://dx.doi.org/10.1007/978-1-4471-5556-0_12.

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Conference papers on the topic "Fusion magnet"

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Cocilovo, Valter. "Magnetic diffusion models for FAST toroidal magnet coils." In 2011 IEEE 24th Symposium on Fusion Engineering (SOFE). IEEE, 2011. http://dx.doi.org/10.1109/sofe.2011.6052275.

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Greenough, N., and J. Lohr. "A magnet current monitor for gyrotron magnet power supplies." In 2013 IEEE 25th Symposium on Fusion Engineering (SOFE). IEEE, 2013. http://dx.doi.org/10.1109/sofe.2013.6635403.

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Nakasone, Yuji, Yukio Takahashi, Arata Nishimura, Tetsuya Suzuki, Hirosada Irie, and Masataka Nakahira. "JSME Construction Standard for Superconducting Magnet of Fusion Facility: “General View of the Code”." In ASME 2009 Pressure Vessels and Piping Conference. ASMEDC, 2009. http://dx.doi.org/10.1115/pvp2009-78018.

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Abstract:
The Japan Society of Mechanical Engineers (JSME) has set up and published the construction standard for superconducting magnet structures to be used in nuclear fusion facilities. The present target of the standard is tokamak-type fusion energy facilities, especially the International Thermonuclear Experimental Reactor called ITER for short. The standard contains rules for structural materials including cryogenic materials, structural design considering magnetic forces, manufacture including welding and installation, nondestructive testing, pressure proof tests and leak tests of toroidal field magnet structures. The standard covers requirements for structural integrity, deformation control, and leak tightness of all the components of the superconducting magnets and their supports except for superconducting strands and electrical insulators. The standard does not cover deterioration which may occur in service as a result of corrosion, radiation effects, or instability of material. The standard consists of seven articles and twelve mandatory and non-mandatory appendices to the articles; i.e., (1) Scope, roles and responsibilities, (2) Materials, (3) Structural design, (4) Fabrication and installation, (5) Non-destructive examination, (6), Pressure and leak testing, and (7) Terms used in general requirement. The present paper describes the general view of the standard. The detailed descriptions of the standard are described by the other papers in this session CS-21, being divided into four categories; i.e., (1) quality assurance, (2) materials, (3) structural design and replacement, and (4) welding, bonding and examination.
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Davis, S., P. Barabaschi, E. Di Pietro, N. Hajnal, V. Tomarchio, M. Verrecchia, M. Wanner, et al. "Status of the JT-60SA magnet system." In 2015 IEEE 26th Symposium on Fusion Engineering (SOFE). IEEE, 2015. http://dx.doi.org/10.1109/sofe.2015.7482274.

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Bykov, V., M. Gasparotto, N. Jaksic, K. Egorov, M. Sochor, L. Sonnerup, J. Simon-Weidner, and M. Rumyancev. "Strategy of Structural Analysis of W7-X Magnet System." In 21st IEEE/NPS Symposium on Fusion Engineering SOFE 05. IEEE, 2005. http://dx.doi.org/10.1109/fusion.2005.252883.

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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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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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Jong, C. T. J., N. Mitchell, and J. Knaster. "ITER Magnet Design Criteria and their Impact on Manufacturing and Assembly." In 2007 IEEE 22nd Symposium on Fusion Engineering. IEEE, 2007. http://dx.doi.org/10.1109/fusion.2007.4337879.

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Zhu, M., W. Hu, S. Mukundan, and N. C. Kar. "Multi-Sensor Fusion Based Permanet Magnet Demagnetization Detection in Permanet Magnet Synchrounous Machines." In 2018 IEEE International Magnetic Conference (INTERMAG). IEEE, 2018. http://dx.doi.org/10.1109/intmag.2018.8508853.

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Dai, Houde, Wanan Yang, Xuke Xia, Shijian Su, and Kui Ma. "A three-axis magnetic sensor array system for permanent magnet tracking." In 2016 IEEE International Conference on Multisensor Fusion and Integration for Intelligent Systems (MFI). IEEE, 2016. http://dx.doi.org/10.1109/mfi.2016.7849533.

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Reports on the topic "Fusion magnet"

1

Cadwallader, L. C. Magnet operating experience review for fusion applications. Office of Scientific and Technical Information (OSTI), November 1991. http://dx.doi.org/10.2172/10138956.

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Cadwallader, L. C. Magnet operating experience review for fusion applications. Office of Scientific and Technical Information (OSTI), November 1991. http://dx.doi.org/10.2172/5393644.

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Zimmermann, M., M. Kazimi, N. Siu, and R. Thome. Failure modes and effects analysis of fusion magnet systems. Office of Scientific and Technical Information (OSTI), December 1988. http://dx.doi.org/10.2172/6317017.

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Chaplin, R. L., H. R. Kerchner, C. E. Klabunde, R. R. Coltman, Oak Ridge National Lab., TN (USA), and Coltman (R.R.), Knoxville, TN (USA)). Stored energy in fusion magnet materials irradiated at low temperatures. Office of Scientific and Technical Information (OSTI), August 1989. http://dx.doi.org/10.2172/5590862.

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Baylor, L. R. Helium mass flow measurement in the International Fusion Superconducting Magnet Test Facility. Office of Scientific and Technical Information (OSTI), August 1986. http://dx.doi.org/10.2172/5489107.

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Heathman, J. H., and J. W. Wohlwend. Mirror Fusion Test Facility-B (MFTF-B) axicell configuration: NbTi magnet system. Design and analysis summary. Volume 1. Office of Scientific and Technical Information (OSTI), May 1985. http://dx.doi.org/10.2172/5292610.

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Ritschel, A. J., and W. L. White. Mirror Fusion Test Facility-B (MFTF-B) axicell configuration: NbTi magnet system. Manufacturing/producibility final report. Volume 2. Office of Scientific and Technical Information (OSTI), May 1985. http://dx.doi.org/10.2172/5365947.

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Wurden, Glen A., Scott C. Hsu, Thomas P. Intrator, C. Grabowski, M. Domonkos, Peter J. Turchi, M. Herrmann, et al. Magneto-Inertial Fusion. Office of Scientific and Technical Information (OSTI), May 2014. http://dx.doi.org/10.2172/1133762.

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Hansen, Stephanie B. Magneto-inertial Fusion. Office of Scientific and Technical Information (OSTI), July 2015. http://dx.doi.org/10.2172/1202011.

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Martens, Daniel, and Scott C. Hsu. Magnetic Probe to Study Plasma Jets for Magneto-Inertial Fusion. Office of Scientific and Technical Information (OSTI), August 2012. http://dx.doi.org/10.2172/1049326.

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