Littérature scientifique sur le sujet « Fusion magnet »
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Articles de revues sur le sujet "Fusion magnet"
WEBER, HARALD W. « RADIATION EFFECTS ON SUPERCONDUCTING FUSION MAGNET COMPONENTS ». International Journal of Modern Physics E 20, no 06 (juin 2011) : 1325–78. http://dx.doi.org/10.1142/s0218301311018526.
Texte intégralBonin, Mélodie, Frédéric-Georges Fontaine et Dominic Larivière. « Comparative Studies of Digestion Techniques for the Dissolution of Neodymium-Based Magnets ». Metals 11, no 8 (21 juillet 2021) : 1149. http://dx.doi.org/10.3390/met11081149.
Texte intégralMenard, 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 (4 février 2019) : 20170440. http://dx.doi.org/10.1098/rsta.2017.0440.
Texte intégralGoll, Dagmar, Felix Trauter, Ralf Loeffler, Thomas Gross et Gerhard Schneider. « Additive Manufacturing of Textured FePrCuB Permanent Magnets ». Micromachines 12, no 9 (31 août 2021) : 1056. http://dx.doi.org/10.3390/mi12091056.
Texte intégralShimamoto, Susumu, et 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.
Texte intégralMiya, 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.
Texte intégralOkuno, K., A. Shikov et N. Koizumi. « Superconducting magnet system in a fusion reactor ». Journal of Nuclear Materials 329-333 (août 2004) : 141–47. http://dx.doi.org/10.1016/j.jnucmat.2004.04.151.
Texte intégralSawan, Mohamed E., et Peter L. Walstrom. « Superconducting Magnet Radiation Effects in Fusion Reactors ». Fusion Technology 10, no 3P2A (novembre 1986) : 741–46. http://dx.doi.org/10.13182/fst86-a24829.
Texte intégralShimamoto, S. « Superconducting magnet development for fusion at JAERI ». Cryogenics 25, no 4 (avril 1985) : 171–77. http://dx.doi.org/10.1016/0011-2275(85)90132-8.
Texte intégralHAMADA, Kazuya, et 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.
Texte intégralThèses sur le sujet "Fusion magnet"
KHOLIA, AKSHAT. « Thermal Hydraulic numerical analysis of Fusion superconducting magnet systems ». Doctoral thesis, Politecnico di Torino, 2013. http://hdl.handle.net/11583/2507886.
Texte intégralCoatanea-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.
Texte intégralThe 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
ZAPPATORE, ANDREA. « Modelling Innovative High Temperature Superconductors for Fusion Applications ». Doctoral thesis, Politecnico di Torino, 2021. http://hdl.handle.net/11583/2935600.
Texte intégralBarber, 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.
Texte intégralCataloged 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.
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.
Texte intégralBayer, 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.
Texte intégralTalami, 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/.
Texte intégralLopes, 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.
Texte intégralThis 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).
Hasnain, Bakhtiyar Asef, et 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.
Texte intégralBruzzone, 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.
Texte intégralLivres sur le sujet "Fusion magnet"
Kulsrud, R. M. Lectures on topics in magnetic reconnection and transport in fusion devices. Nagoya, Japan : Institute of Plasma Physics, Nagoya University, 1986.
Trouver le texte intégral1949-, Yamazaki K., dir. Design scalings and optimizations for super-conducting large helical devices. Nagoya, Japan : National Institute for Fusion Science, 1990.
Trouver le texte intégralUnited States. National Aeronautics and Space Administration., dir. Investigation of the possibility of using nuclear magnetic spin alignment : Final report. [Huntsville, Ala.] : DIR, Inc., 1998.
Trouver le texte intégralGurūpu, Kakuyūgō Kagaku Kenkyūjo Ōgata Herikaru Sōchi Sekkei. Ōgata herikaru sōchi keikaku. [Tokyo] : Monbushō Kakuyūgō Kagaku Kenkyūjo Ōgata Herikaru Sōchi Sekkei Gurūpu, 1990.
Trouver le texte intégralA, Iiyoshi, dir. Design study of the large helical device. Nagoya, Japan : National Institute for Fusion Science, 1990.
Trouver le texte intégralKakuyūgō 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.
Trouver le texte intégralDolan, Thomas J., Ralph W. Moir, Wallace Manheimer, Lee C. Cadwallader et Martin J. Neumann. Magnetic Fusion Technology. Springer, 2014.
Trouver le texte intégralDolan, Thomas J. Magnetic Fusion Technology. Springer, 2016.
Trouver le texte intégralDolan, Thomas J. Magnetic Fusion Technology. Springer, 2014.
Trouver le texte intégralRaum, Elizabeth. What's the Attraction ? (Raintree Fusion : Magnetism). Raintree, 2006.
Trouver le texte intégralChapitres de livres sur le sujet "Fusion magnet"
Shimamoto, S. « Development of Superconducting Magnet for Fusion Power ». Dans Advances in Superconductivity, 43–49. Tokyo : Springer Japan, 1989. http://dx.doi.org/10.1007/978-4-431-68084-0_6.
Texte intégralFietz, William A. « Experience in the Operation of the International Fusion Superconducting Magnet Test Facility ». Dans Advances in Cryogenic Engineering, 517–28. Boston, MA : Springer US, 1990. http://dx.doi.org/10.1007/978-1-4613-0639-9_61.
Texte intégralGori, Roberto E., et Pierluigi Zaccaria. « Plastic Bending Large Displacement Analysis and Spring-Back of a Conductor Jacket of a Superconducting Magnet for Fusion Reactors ». Dans 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.
Texte intégralHumer, K., P. Rosenkranz, H. W. Weber, J. A. Rice et C. S. Hazelton. « Mechanical Strength, Swelling and Weight Loss of Inorganic Fusion Magnet Insulation Systems Following Reactor Irradiation ». Dans Advances in Cryogenic Engineering Materials, 135–41. Boston, MA : Springer US, 2000. http://dx.doi.org/10.1007/978-1-4615-4293-3_17.
Texte intégralDolan, Thomas J., et Denis P. Ivanov. « Superconducting Magnets ». Dans Magnetic Fusion Technology, 119–74. London : Springer London, 2013. http://dx.doi.org/10.1007/978-1-4471-5556-0_4.
Texte intégralDolan, Thomas J. « Pulsed and Water-Cooled Magnets ». Dans Magnetic Fusion Technology, 71–118. London : Springer London, 2013. http://dx.doi.org/10.1007/978-1-4471-5556-0_3.
Texte intégralDolan, Thomas J., et Alexander Parrish. « Introduction ». Dans Magnetic Fusion Technology, 1–44. London : Springer London, 2013. http://dx.doi.org/10.1007/978-1-4471-5556-0_1.
Texte intégralDolan, Thomas J. « Cryogenic Systems ». Dans Magnetic Fusion Technology, 491–511. London : Springer London, 2013. http://dx.doi.org/10.1007/978-1-4471-5556-0_10.
Texte intégralDolan, Thomas J., Alan E. Costley et Jana Brotankova. « Plasma Diagnostics ». Dans Magnetic Fusion Technology, 513–617. London : Springer London, 2013. http://dx.doi.org/10.1007/978-1-4471-5556-0_11.
Texte intégralDolan, Thomas J., et Lee C. Cadwallader. « Safety and Environment ». Dans Magnetic Fusion Technology, 619–52. London : Springer London, 2013. http://dx.doi.org/10.1007/978-1-4471-5556-0_12.
Texte intégralActes de conférences sur le sujet "Fusion magnet"
Cocilovo, Valter. « Magnetic diffusion models for FAST toroidal magnet coils ». Dans 2011 IEEE 24th Symposium on Fusion Engineering (SOFE). IEEE, 2011. http://dx.doi.org/10.1109/sofe.2011.6052275.
Texte intégralGreenough, N., et J. Lohr. « A magnet current monitor for gyrotron magnet power supplies ». Dans 2013 IEEE 25th Symposium on Fusion Engineering (SOFE). IEEE, 2013. http://dx.doi.org/10.1109/sofe.2013.6635403.
Texte intégralNakasone, Yuji, Yukio Takahashi, Arata Nishimura, Tetsuya Suzuki, Hirosada Irie et Masataka Nakahira. « JSME Construction Standard for Superconducting Magnet of Fusion Facility : “General View of the Code” ». Dans ASME 2009 Pressure Vessels and Piping Conference. ASMEDC, 2009. http://dx.doi.org/10.1115/pvp2009-78018.
Texte intégralDavis, S., P. Barabaschi, E. Di Pietro, N. Hajnal, V. Tomarchio, M. Verrecchia, M. Wanner et al. « Status of the JT-60SA magnet system ». Dans 2015 IEEE 26th Symposium on Fusion Engineering (SOFE). IEEE, 2015. http://dx.doi.org/10.1109/sofe.2015.7482274.
Texte intégralBykov, V., M. Gasparotto, N. Jaksic, K. Egorov, M. Sochor, L. Sonnerup, J. Simon-Weidner et M. Rumyancev. « Strategy of Structural Analysis of W7-X Magnet System ». Dans 21st IEEE/NPS Symposium on Fusion Engineering SOFE 05. IEEE, 2005. http://dx.doi.org/10.1109/fusion.2005.252883.
Texte intégralGallix, R., Y. Fu, C. Jong, P. Y. Lee, B. L. Hou et G. D. Jian. « Updated design of the ITER magnet system gravity supports ». Dans 2009 23rd IEEE/NPSS Symposium on Fusion Engineering - SOFE. IEEE, 2009. http://dx.doi.org/10.1109/fusion.2009.5226496.
Texte intégralSborchia, 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 ». Dans 2011 IEEE 24th Symposium on Fusion Engineering (SOFE). IEEE, 2011. http://dx.doi.org/10.1109/sofe.2011.6052218.
Texte intégralJong, C. T. J., N. Mitchell et J. Knaster. « ITER Magnet Design Criteria and their Impact on Manufacturing and Assembly ». Dans 2007 IEEE 22nd Symposium on Fusion Engineering. IEEE, 2007. http://dx.doi.org/10.1109/fusion.2007.4337879.
Texte intégralZhu, M., W. Hu, S. Mukundan et N. C. Kar. « Multi-Sensor Fusion Based Permanet Magnet Demagnetization Detection in Permanet Magnet Synchrounous Machines ». Dans 2018 IEEE International Magnetic Conference (INTERMAG). IEEE, 2018. http://dx.doi.org/10.1109/intmag.2018.8508853.
Texte intégralDai, Houde, Wanan Yang, Xuke Xia, Shijian Su et Kui Ma. « A three-axis magnetic sensor array system for permanent magnet tracking ». Dans 2016 IEEE International Conference on Multisensor Fusion and Integration for Intelligent Systems (MFI). IEEE, 2016. http://dx.doi.org/10.1109/mfi.2016.7849533.
Texte intégralRapports d'organisations sur le sujet "Fusion magnet"
Cadwallader, L. C. Magnet operating experience review for fusion applications. Office of Scientific and Technical Information (OSTI), novembre 1991. http://dx.doi.org/10.2172/10138956.
Texte intégralCadwallader, L. C. Magnet operating experience review for fusion applications. Office of Scientific and Technical Information (OSTI), novembre 1991. http://dx.doi.org/10.2172/5393644.
Texte intégralZimmermann, M., M. Kazimi, N. Siu et R. Thome. Failure modes and effects analysis of fusion magnet systems. Office of Scientific and Technical Information (OSTI), décembre 1988. http://dx.doi.org/10.2172/6317017.
Texte intégralChaplin, R. L., H. R. Kerchner, C. E. Klabunde, R. R. Coltman, Oak Ridge National Lab., TN (USA) et Coltman (R.R.), Knoxville, TN (USA)). Stored energy in fusion magnet materials irradiated at low temperatures. Office of Scientific and Technical Information (OSTI), août 1989. http://dx.doi.org/10.2172/5590862.
Texte intégralBaylor, L. R. Helium mass flow measurement in the International Fusion Superconducting Magnet Test Facility. Office of Scientific and Technical Information (OSTI), août 1986. http://dx.doi.org/10.2172/5489107.
Texte intégralHeathman, J. H., et 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), mai 1985. http://dx.doi.org/10.2172/5292610.
Texte intégralRitschel, A. J., et 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), mai 1985. http://dx.doi.org/10.2172/5365947.
Texte intégralWurden, 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), mai 2014. http://dx.doi.org/10.2172/1133762.
Texte intégralHansen, Stephanie B. Magneto-inertial Fusion. Office of Scientific and Technical Information (OSTI), juillet 2015. http://dx.doi.org/10.2172/1202011.
Texte intégralMartens, Daniel, et Scott C. Hsu. Magnetic Probe to Study Plasma Jets for Magneto-Inertial Fusion. Office of Scientific and Technical Information (OSTI), août 2012. http://dx.doi.org/10.2172/1049326.
Texte intégral