Literatura académica sobre el tema "Fusion magnet"
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Artículos de revistas sobre el tema "Fusion magnet"
WEBER, HARALD W. "RADIATION EFFECTS ON SUPERCONDUCTING FUSION MAGNET COMPONENTS". International Journal of Modern Physics E 20, n.º 06 (junio de 2011): 1325–78. http://dx.doi.org/10.1142/s0218301311018526.
Texto completoBonin, Mélodie, Frédéric-Georges Fontaine y Dominic Larivière. "Comparative Studies of Digestion Techniques for the Dissolution of Neodymium-Based Magnets". Metals 11, n.º 8 (21 de julio de 2021): 1149. http://dx.doi.org/10.3390/met11081149.
Texto completoMenard, 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, n.º 2141 (4 de febrero de 2019): 20170440. http://dx.doi.org/10.1098/rsta.2017.0440.
Texto completoGoll, Dagmar, Felix Trauter, Ralf Loeffler, Thomas Gross y Gerhard Schneider. "Additive Manufacturing of Textured FePrCuB Permanent Magnets". Micromachines 12, n.º 9 (31 de agosto de 2021): 1056. http://dx.doi.org/10.3390/mi12091056.
Texto completoShimamoto, Susumu y Takashi Satow. "Superconducting Magnet Development for Fusion Reactor". IEEJ Transactions on Power and Energy 119, n.º 11 (1999): 1143–45. http://dx.doi.org/10.1541/ieejpes1990.119.11_1143.
Texto completoMiya, Kenzo. "Super conducting magnet technologies for fusion reactor." Kakuyūgō kenkyū 56, n.º 2 (1986): 105–14. http://dx.doi.org/10.1585/jspf1958.56.105.
Texto completoOkuno, K., A. Shikov y N. Koizumi. "Superconducting magnet system in a fusion reactor". Journal of Nuclear Materials 329-333 (agosto de 2004): 141–47. http://dx.doi.org/10.1016/j.jnucmat.2004.04.151.
Texto completoSawan, Mohamed E. y Peter L. Walstrom. "Superconducting Magnet Radiation Effects in Fusion Reactors". Fusion Technology 10, n.º 3P2A (noviembre de 1986): 741–46. http://dx.doi.org/10.13182/fst86-a24829.
Texto completoShimamoto, S. "Superconducting magnet development for fusion at JAERI". Cryogenics 25, n.º 4 (abril de 1985): 171–77. http://dx.doi.org/10.1016/0011-2275(85)90132-8.
Texto completoHAMADA, Kazuya y Norikiyo KOIZUMI. "Electromagnetic Phenomenon in Superconducting Magnet for Fusion Facility. Forced Flow Superconducting Magnet." Journal of Plasma and Fusion Research 78, n.º 7 (2002): 616–24. http://dx.doi.org/10.1585/jspf.78.616.
Texto completoTesis sobre el tema "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.
Texto completoCoatanea-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.
Texto completoThe 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.
Texto completoBarber, 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.
Texto completoCataloged 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.
Texto completoBayer, 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.
Texto completoTalami, 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/.
Texto completoLopes, 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.
Texto completoThis 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 y 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.
Texto completoBruzzone, 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.
Texto completoLibros sobre el tema "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.
Buscar texto completo1949-, Yamazaki K., ed. Design scalings and optimizations for super-conducting large helical devices. Nagoya, Japan: National Institute for Fusion Science, 1990.
Buscar texto completoUnited States. National Aeronautics and Space Administration., ed. Investigation of the possibility of using nuclear magnetic spin alignment: Final report. [Huntsville, Ala.]: DIR, Inc., 1998.
Buscar texto completoGurūpu, Kakuyūgō Kagaku Kenkyūjo Ōgata Herikaru Sōchi Sekkei. Ōgata herikaru sōchi keikaku. [Tokyo]: Monbushō Kakuyūgō Kagaku Kenkyūjo Ōgata Herikaru Sōchi Sekkei Gurūpu, 1990.
Buscar texto completoA, Iiyoshi, ed. Design study of the large helical device. Nagoya, Japan: National Institute for Fusion Science, 1990.
Buscar texto completoKakuyūgō 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.
Buscar texto completoDolan, Thomas J., Ralph W. Moir, Wallace Manheimer, Lee C. Cadwallader y Martin J. Neumann. Magnetic Fusion Technology. Springer, 2014.
Buscar texto completoDolan, Thomas J. Magnetic Fusion Technology. Springer, 2016.
Buscar texto completoDolan, Thomas J. Magnetic Fusion Technology. Springer, 2014.
Buscar texto completoRaum, Elizabeth. What's the Attraction? (Raintree Fusion: Magnetism). Raintree, 2006.
Buscar texto completoCapítulos de libros sobre el tema "Fusion magnet"
Shimamoto, S. "Development of Superconducting Magnet for Fusion Power". En Advances in Superconductivity, 43–49. Tokyo: Springer Japan, 1989. http://dx.doi.org/10.1007/978-4-431-68084-0_6.
Texto completoFietz, William A. "Experience in the Operation of the International Fusion Superconducting Magnet Test Facility". En Advances in Cryogenic Engineering, 517–28. Boston, MA: Springer US, 1990. http://dx.doi.org/10.1007/978-1-4613-0639-9_61.
Texto completoGori, Roberto E. y Pierluigi Zaccaria. "Plastic Bending Large Displacement Analysis and Spring-Back of a Conductor Jacket of a Superconducting Magnet for Fusion Reactors". En 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.
Texto completoHumer, K., P. Rosenkranz, H. W. Weber, J. A. Rice y C. S. Hazelton. "Mechanical Strength, Swelling and Weight Loss of Inorganic Fusion Magnet Insulation Systems Following Reactor Irradiation". En Advances in Cryogenic Engineering Materials, 135–41. Boston, MA: Springer US, 2000. http://dx.doi.org/10.1007/978-1-4615-4293-3_17.
Texto completoDolan, Thomas J. y Denis P. Ivanov. "Superconducting Magnets". En Magnetic Fusion Technology, 119–74. London: Springer London, 2013. http://dx.doi.org/10.1007/978-1-4471-5556-0_4.
Texto completoDolan, Thomas J. "Pulsed and Water-Cooled Magnets". En Magnetic Fusion Technology, 71–118. London: Springer London, 2013. http://dx.doi.org/10.1007/978-1-4471-5556-0_3.
Texto completoDolan, Thomas J. y Alexander Parrish. "Introduction". En Magnetic Fusion Technology, 1–44. London: Springer London, 2013. http://dx.doi.org/10.1007/978-1-4471-5556-0_1.
Texto completoDolan, Thomas J. "Cryogenic Systems". En Magnetic Fusion Technology, 491–511. London: Springer London, 2013. http://dx.doi.org/10.1007/978-1-4471-5556-0_10.
Texto completoDolan, Thomas J., Alan E. Costley y Jana Brotankova. "Plasma Diagnostics". En Magnetic Fusion Technology, 513–617. London: Springer London, 2013. http://dx.doi.org/10.1007/978-1-4471-5556-0_11.
Texto completoDolan, Thomas J. y Lee C. Cadwallader. "Safety and Environment". En Magnetic Fusion Technology, 619–52. London: Springer London, 2013. http://dx.doi.org/10.1007/978-1-4471-5556-0_12.
Texto completoActas de conferencias sobre el tema "Fusion magnet"
Cocilovo, Valter. "Magnetic diffusion models for FAST toroidal magnet coils". En 2011 IEEE 24th Symposium on Fusion Engineering (SOFE). IEEE, 2011. http://dx.doi.org/10.1109/sofe.2011.6052275.
Texto completoGreenough, N. y J. Lohr. "A magnet current monitor for gyrotron magnet power supplies". En 2013 IEEE 25th Symposium on Fusion Engineering (SOFE). IEEE, 2013. http://dx.doi.org/10.1109/sofe.2013.6635403.
Texto completoNakasone, Yuji, Yukio Takahashi, Arata Nishimura, Tetsuya Suzuki, Hirosada Irie y Masataka Nakahira. "JSME Construction Standard for Superconducting Magnet of Fusion Facility: “General View of the Code”". En ASME 2009 Pressure Vessels and Piping Conference. ASMEDC, 2009. http://dx.doi.org/10.1115/pvp2009-78018.
Texto completoDavis, S., P. Barabaschi, E. Di Pietro, N. Hajnal, V. Tomarchio, M. Verrecchia, M. Wanner et al. "Status of the JT-60SA magnet system". En 2015 IEEE 26th Symposium on Fusion Engineering (SOFE). IEEE, 2015. http://dx.doi.org/10.1109/sofe.2015.7482274.
Texto completoBykov, V., M. Gasparotto, N. Jaksic, K. Egorov, M. Sochor, L. Sonnerup, J. Simon-Weidner y M. Rumyancev. "Strategy of Structural Analysis of W7-X Magnet System". En 21st IEEE/NPS Symposium on Fusion Engineering SOFE 05. IEEE, 2005. http://dx.doi.org/10.1109/fusion.2005.252883.
Texto completoGallix, R., Y. Fu, C. Jong, P. Y. Lee, B. L. Hou y G. D. Jian. "Updated design of the ITER magnet system gravity supports". En 2009 23rd IEEE/NPSS Symposium on Fusion Engineering - SOFE. IEEE, 2009. http://dx.doi.org/10.1109/fusion.2009.5226496.
Texto completoSborchia, 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". En 2011 IEEE 24th Symposium on Fusion Engineering (SOFE). IEEE, 2011. http://dx.doi.org/10.1109/sofe.2011.6052218.
Texto completoJong, C. T. J., N. Mitchell y J. Knaster. "ITER Magnet Design Criteria and their Impact on Manufacturing and Assembly". En 2007 IEEE 22nd Symposium on Fusion Engineering. IEEE, 2007. http://dx.doi.org/10.1109/fusion.2007.4337879.
Texto completoZhu, M., W. Hu, S. Mukundan y N. C. Kar. "Multi-Sensor Fusion Based Permanet Magnet Demagnetization Detection in Permanet Magnet Synchrounous Machines". En 2018 IEEE International Magnetic Conference (INTERMAG). IEEE, 2018. http://dx.doi.org/10.1109/intmag.2018.8508853.
Texto completoDai, Houde, Wanan Yang, Xuke Xia, Shijian Su y Kui Ma. "A three-axis magnetic sensor array system for permanent magnet tracking". En 2016 IEEE International Conference on Multisensor Fusion and Integration for Intelligent Systems (MFI). IEEE, 2016. http://dx.doi.org/10.1109/mfi.2016.7849533.
Texto completoInformes sobre el tema "Fusion magnet"
Cadwallader, L. C. Magnet operating experience review for fusion applications. Office of Scientific and Technical Information (OSTI), noviembre de 1991. http://dx.doi.org/10.2172/10138956.
Texto completoCadwallader, L. C. Magnet operating experience review for fusion applications. Office of Scientific and Technical Information (OSTI), noviembre de 1991. http://dx.doi.org/10.2172/5393644.
Texto completoZimmermann, M., M. Kazimi, N. Siu y R. Thome. Failure modes and effects analysis of fusion magnet systems. Office of Scientific and Technical Information (OSTI), diciembre de 1988. http://dx.doi.org/10.2172/6317017.
Texto completoChaplin, R. L., H. R. Kerchner, C. E. Klabunde, R. R. Coltman, Oak Ridge National Lab., TN (USA) y Coltman (R.R.), Knoxville, TN (USA)). Stored energy in fusion magnet materials irradiated at low temperatures. Office of Scientific and Technical Information (OSTI), agosto de 1989. http://dx.doi.org/10.2172/5590862.
Texto completoBaylor, L. R. Helium mass flow measurement in the International Fusion Superconducting Magnet Test Facility. Office of Scientific and Technical Information (OSTI), agosto de 1986. http://dx.doi.org/10.2172/5489107.
Texto completoHeathman, J. H. y 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), mayo de 1985. http://dx.doi.org/10.2172/5292610.
Texto completoRitschel, A. J. y 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), mayo de 1985. http://dx.doi.org/10.2172/5365947.
Texto completoWurden, 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), mayo de 2014. http://dx.doi.org/10.2172/1133762.
Texto completoHansen, Stephanie B. Magneto-inertial Fusion. Office of Scientific and Technical Information (OSTI), julio de 2015. http://dx.doi.org/10.2172/1202011.
Texto completoMartens, Daniel y Scott C. Hsu. Magnetic Probe to Study Plasma Jets for Magneto-Inertial Fusion. Office of Scientific and Technical Information (OSTI), agosto de 2012. http://dx.doi.org/10.2172/1049326.
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