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Artículos de revistas sobre el tema "Fusion magnet"

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Autor: Grafiati

Publicado: 14 de marzo de 2023

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1

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.

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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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2

Bonin, 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.

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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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3

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, n.º 2141 (4 de febrero de 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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4

Goll, 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.

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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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5

Shimamoto, 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.

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6

Miya, 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.

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7

Okuno, 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.

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8

Sawan, 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.

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9

Shimamoto, 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.

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10

HAMADA, 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.

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11

Okada, Toichi. "Superconducting technology for nuclear fusion facilities. 4. Fusion magnet related technology." Kakuyūgō kenkyū 62, n.º 1 (1989): 20–30. http://dx.doi.org/10.1585/jspf1958.62.20.

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12

Zhang, Yi, Yuejin Tang, Ying Xu, Zhong Xia y Li Ren. "Numerical Simulation of a No-Insulation BSCCO Toroidal Magnet Applied in Magnetic Confinement Fusion". Science and Technology of Nuclear Installations 2018 (31 de mayo de 2018): 1–10. http://dx.doi.org/10.1155/2018/2914036.

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At present, the Tokamak has become a mainstream form of the magnetic confinement fusion device. The toroidal field (TF) magnet in the Tokamak system is required to generate a high-steady field to confine and shape the high temperature plasma. To secure high current density and high thermal stability, the no-insulation (NI) winding technique is used in the fabrication of the TF magnet. During plasma operation, heat is generated in the TF magnet caused by the interaction with central solenoid (CS) coils, poloidal field (PF) coils, and the plasma current. The heat generated in NI coils is complex owing to the existence of current flow between adjacent turns. Thus, it is necessary to calculate the thermal problems. Taking into consideration the effect of turn-to-turn contact resistance, this paper presents the thermal behavior of a NI toroidal magnet under different operating conditions. The NI toroidal magnet is composed of 10 double-pancake (DP) coils wound with BSCCO tapes. The analysis procedure combines the finite element method (FEM) with an equivalent circuit model. This analysis has applicability and practical directive to the design of cryogenic cooling system for NI toroidal magnet.

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13

Zhu, Min, Wensong Hu y Narayan C. Kar. "Multi-Sensor Fusion-Based Permanent Magnet Demagnetization Detection in Permanent Magnet Synchronous Machines". IEEE Transactions on Magnetics 54, n.º 11 (noviembre de 2018): 1–6. http://dx.doi.org/10.1109/tmag.2018.2836182.

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14

Koshelev, S., T. Tope, J. Theilacker, V. Nikolic, G. Velev, E. Voirin, A. J. Marone y P. E. Kovach. "Design of the cryostat for High Field Vertical Magnet Testing Facility at Fermilab". IOP Conference Series: Materials Science and Engineering 1240, n.º 1 (1 de mayo de 2022): 012081. http://dx.doi.org/10.1088/1757-899x/1240/1/012081.

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Abstract High Field Vertical Magnet Test Facility (HFVMTF) is a joint project between the Office of High Energy Physics (HEP) and the Office of Fusion Energy Sciences (FES). Its construction is currently under way at Fermi National Accelerator Laboratory (Fermilab). As a part of the project a new double bath superfluid helium cryostat has been designed. The cryostat can accommodate magnets with up to 20 tonne weight and 1.3 m diameter. This paper discusses challenges and solutions for cryostat, lambda plate and heat exchanger design, and presents results of performance analysis.

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15

Yoshida, Kiyoshi. "Superconducting magnet technology for the Tokamak fusion reactor." Kakuyūgō kenkyū 62, n.º 3 (1989): 185–200. http://dx.doi.org/10.1585/jspf1958.62.185.

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16

YANAGI, Nagato, Satoshi ITO, Yoshiro TERAZAKI, Kyohei NATSUME, Hitoshi TAMURA, Shinji HAMAGUCHI, Toshiyuki MITO et al. "Feasibility of HTS Magnet Option for Fusion Reactors". Plasma and Fusion Research 9 (2014): 1405013. http://dx.doi.org/10.1585/pfr.9.1405013.

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17

Latkowski, J. F. y W. R. Meier. "Heavy-Ion Fusion Final Focus Magnet Shielding Designs". Fusion Technology 39, n.º 2P2 (marzo de 2001): 798–803. http://dx.doi.org/10.13182/fst01-a11963337.

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18

Zhai, Y., C. Kessel, L. El-Guebaly y P. Titus. "Magnet Design Considerations for Fusion Nuclear Science Facility". IEEE Transactions on Applied Superconductivity 26, n.º 4 (junio de 2016): 1–5. http://dx.doi.org/10.1109/tasc.2016.2532921.

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19

Fetzko, R. y T. Hordubay. "Welding and brazing the westinghouse fusion magnet coil". IEEE Transactions on Magnetics 23, n.º 2 (marzo de 1987): 1425–27. http://dx.doi.org/10.1109/tmag.1987.1064827.

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20

Minervini, J. V. y J. H. Schultz. "US fusion program requirements for superconducting magnet research". IEEE Transactions on Appiled Superconductivity 13, n.º 2 (junio de 2003): 1524–29. http://dx.doi.org/10.1109/tasc.2003.812766.

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21

Bromberg, L., H. Hashizume, S. Ito, J. V. Minervini y N. Yanagi. "Status of High Temperature Superconducting Fusion Magnet Development". Fusion Science and Technology 60, n.º 2 (agosto de 2011): 635–42. http://dx.doi.org/10.13182/fst11-a12455.

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22

Pasler, Volker y Dmitry Klimenko. "Safety of Fusion Magnets: Model Experiments to High Current ARCS Propagating along the Busbars of Large Fusion Magnet Coils". Fusion Science and Technology 56, n.º 2 (agosto de 2009): 804–8. http://dx.doi.org/10.13182/fst09-a9008.

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23

Windridge, Melanie. "Smaller and quicker with spherical tokamaks and high-temperature superconductors". Philosophical Transactions of the Royal Society A: Mathematical, Physical and Engineering Sciences 377, n.º 2141 (4 de febrero de 2019): 20170438. http://dx.doi.org/10.1098/rsta.2017.0438.

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Research in the 1970s and 1980s by Sykes, Peng, Jassby and others showed the theoretical advantage of the spherical tokamak (ST) shape. Experiments on START and MAST at Culham throughout the 1990s and 2000s, alongside other international STs like NSTX at the Princeton Plasma Physics Laboratory, confirmed their increased efficiency (namely operation at higher beta) and tested the plasma physics in new regimes. However, while interesting devices for study, the perceived technological difficulties due to the compact shape initially prevented STs being seriously considered as viable power plants. Then, in the 2010s, high-temperature superconductor (HTS) materials became available as a reliable engineering material, fabricated into long tapes suitable for winding into magnets. Realizing the advantages of this material and its possibilities for fusion, Tokamak Energy proposed a new ST path to fusion power and began working on demonstrating the viability of HTS for fusion magnets. The company is now operating a compact tokamak with copper magnets, R 0 ∼ 0.4 m, R / a ∼ 1.8, and target I p = 2MA, B t0 = 3 T, while in parallel developing a 5 T HTS demonstrator tokamak magnet. Here we discuss why HTS can be a game-changer for tokamak fusion. We outline Tokamak Energy's solution for a faster way to fusion and discuss plans and progress, including benefits of smaller devices on the development path and advantages of modularity in power plants. We will indicate some of the key research areas in compact tokamaks and introduce the physics considerations behind the ST approach, to be further developed in the subsequent paper by Alan Costley. This article is part of a discussion meeting issue ‘Fusion energy using tokamaks: can development be accelerated?’.

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24

FALTENS, A., A. LIETZKE, G. SABBI, P. SEIDL, S. LUND, B. MANAHAN, N. MARTOVETSKY et al. "Progress in the development of superconducting quadrupoles for heavy ion fusion". Laser and Particle Beams 20, n.º 4 (octubre de 2002): 617–20. http://dx.doi.org/10.1017/s0263034602204267.

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The heavy ion fusion program is developing single aperture superconducting quadrupoles based on NbTi conductor, for use in the High Current Experiment at Lawrence Berkeley National Laboratory. Following the fabrication and testing of prototypes using two different approaches, a baseline design has been selected and further optimized. A prototype cryostat for a quadrupole doublet, with features to accommodate induction acceleration modules, is being fabricated. The single aperture magnet was derived from a conceptual design of a quadrupole array magnet for multibeam transport. Progress on the development of superconducting quadrupole arrays for future experiments is also reported.

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25

Clery, Daniel. "Magnet tests kick off bid for net fusion energy". Science 371, n.º 6534 (11 de marzo de 2021): 1091. http://dx.doi.org/10.1126/science.371.6534.1091.

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26

Titus, Peter H. "Fusion Ignition Research Experiment (FIRE) Magnet System Structural Analyses". Fusion Technology 39, n.º 2P2 (marzo de 2001): 383–88. http://dx.doi.org/10.13182/fst01-a11963264.

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27

Wu, Zhixiong, Rongjin Huang, Chuanjun Huang y Laifeng Li. "Properties of radiation stable insulation composites for fusion magnet". Journal of Physics: Conference Series 897 (septiembre de 2017): 012004. http://dx.doi.org/10.1088/1742-6596/897/1/012004.

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28

Shimada, R., J. Kondoh, Y. Satou y S. Tsuji-Iio. "Innovative application of a magnet system to fusion power". Fusion Engineering and Design 41, n.º 1-4 (septiembre de 1998): 223–29. http://dx.doi.org/10.1016/s0920-3796(98)00203-8.

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29

Hahn, P. A., H. Hoch, H. W. Weber, R. C. Birtcher y B. S. Brown. "Simulation of fusion reactor conditions for superconducting magnet materials". Journal of Nuclear Materials 141-143 (noviembre de 1986): 405–9. http://dx.doi.org/10.1016/s0022-3115(86)80074-5.

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30

Zhai, Yuhu, Peter Titus, Charles Kessel y Laila El-Guebaly. "Conceptual magnet design study for fusion nuclear science facility". Fusion Engineering and Design 135 (octubre de 2018): 324–36. http://dx.doi.org/10.1016/j.fusengdes.2017.06.028.

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31

Shikov, A., A. Nikulin, V. Pantsyrnyi, A. Vorobieva, G. Vedernikov, A. Silaev, E. Dergunova, S. Soudiev y I. Akimov. "Russian superconducting materials for magnet systems of fusion reactors". Journal of Nuclear Materials 283-287 (diciembre de 2000): 968–72. http://dx.doi.org/10.1016/s0022-3115(00)00166-5.

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32

SHIMAMOTO, Susumu. "Research and Development of Superconducting Magnet for Fusion Power". Journal of Nuclear Science and Technology 26, n.º 1 (enero de 1989): 184–88. http://dx.doi.org/10.1080/18811248.1989.9734286.

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33

Nishijima, S., T. Okada, T. Hirokawa, J. Yasuda y Y. Iwasaki. "Radiation damage of organic composite material for fusion magnet". Cryogenics 31, n.º 4 (abril de 1991): 273–76. http://dx.doi.org/10.1016/0011-2275(91)90092-b.

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34

Zucchetti, M., E. Medda y G. Maizza. "Nuclear properties of magnet structural materials for fusion reactors". Journal of Nuclear Materials 179-181 (marzo de 1991): 1123–26. http://dx.doi.org/10.1016/0022-3115(91)90289-j.

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35

Seo, Kazutaka, Toshiyuki Mito, Shuma Kawabata, Tadashi Ichihara y Mitsuru Hasegawa. "Electromagnetic behavior of lap-joints for fusion magnet system". Cryogenics 47, n.º 1 (enero de 2007): 25–30. http://dx.doi.org/10.1016/j.cryogenics.2006.08.009.

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36

Wang, Qiuliang, Jianhua Liu, Jinxing Zheng, Jinggang Qin, Yanwei Ma, Qingjin Xu, Dongliang Wang et al. "Progress of ultra-high-field superconducting magnets in China". Superconductor Science and Technology 35, n.º 2 (30 de diciembre de 2021): 023001. http://dx.doi.org/10.1088/1361-6668/ac3f9b.

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Abstract High magnetic fields play a critical role in the development of modern science and technology, breeding many significant scientific discoveries and boosting the generation of new technologies. In the last few years, China has undertaken a great deal of work on the application of ultra-high-field (UHF) superconducting magnet technology, such as for the Synergetic Extreme Condition User Facility in Beijing, the UHF nuclear magnetic resonance/magnetic resonance imaging, nuclear fusion energy, particle accelerator, and so on. This paper reports the research status of UHF superconducting magnets in China from different perspectives, including design options, technical features, experimental progress, opportunities, and challenges.

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37

Fietz, W. A., J. F. Ellis, P. N. Haubenreich, S. W. Schwenterly y R. E. Stamps. "Experience with Operation of a Large Magnet System in the International Fusion Superconducting Magnet Test Facility". Fusion Technology 8, n.º 1P2A (julio de 1985): 817–22. http://dx.doi.org/10.13182/fst85-a40134.

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38

Sun, Eric Qiuli. "Multi-scale nonlinear stress analysis of Nb₃Sn superconducting accelerator magnets". Superconductor Science and Technology 35, n.º 4 (14 de marzo de 2022): 045019. http://dx.doi.org/10.1088/1361-6668/ac5a11.

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Abstract A multi-scale nonlinear procedure to analyze the stress in Nb3Sn superconducting accelerator magnets is presented to address one of the most challenging obstacles currently facing the successful development of high-field superconducting magnets—the issue of stress management. The study demonstrates that gasket materials (special nonlinear materials) are capable of modeling the complex nonlinear deformation behavior of insulation layers within the Nb3Sn coil block and that Hill materials (orthotropic materials utilizing the Hill yield criterion) are suitable to enable homogenization of the filamentary regions and the resin-impregnated Nb3Sn Rutherford cables. With the whole magnet under preload, cool-down, and Lorentz forces, the nonlinear behavior of the Nb3Sn coil was simulated, in three orthongonal axes, using the combined properties of the gasket materials (insulation layers) and Hill materials (resin-impreganted cable). The procedure makes very few assumptions with regard to material properties because it incorporates actual measured stress–strain curves in the analysis. The coil was simulated to the level of detail of the insulation layers and resin-impregnated cables. The computed compressive azimuthal stresses of the cables were used to assess stress-induced performance degradation. Through submodeling, the area-weighted average axial strains of the strands were computed and employed to evaluate the strain-induced performance degradation. The overall performance degradation of the Nb3Sn coil was thus obtained, and this information was subsequently used to guide the design of the overall magnet. Besides Nb3Sn magnets, this versatile procedure can also be employed in the design of LTS, HTS, and room temperature magnets or of any structures ultilizing composite materials; specifically, it can be used to manage the stress and strain of HTS fusion magnets.

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39

Tamura, H., N. Yanagi, T. Goto, K. Takahata, S. Imagawa y A. Sagara. "Methodological Study of Structural Analysis of LHD-Type Fusion Magnet". Physics Procedia 36 (2012): 1071–76. http://dx.doi.org/10.1016/j.phpro.2012.06.108.

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40

Tamura, H., N. Yanagi, T. Goto, K. Takahata, S. Imagawa y A. Sagara. "Methodological Study of Structural Analysis of LHD-type Fusion Magnet". Physics Procedia 36 (2012): 1077–82. http://dx.doi.org/10.1016/j.phpro.2012.06.109.

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41

Kaneko, H., N. Yanagi, T. Satow, T. Mito, K. Takahata y J. Yamamoto. "Flux jump in solid multistrand superconducting cable for fusion magnet". Cryogenics 35, n.º 10 (enero de 1995): 611–22. http://dx.doi.org/10.1016/s0011-2275(99)80001-0.

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42

Okada, T., S. Nishijima, C. Ichihara y H. Yamaoka. "Activation problems of superconducting magnet materials used in fusion reactors". Journal of Nuclear Materials 133-134 (agosto de 1985): 791–94. http://dx.doi.org/10.1016/0022-3115(85)90259-4.

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43

Tamura, H., T. Goto, J. Miyazawa, T. Tanaka y N. Yanagi. "Topology optimization for superconducting magnet system in helical fusion reactor". Journal of Physics: Conference Series 1559 (junio de 2020): 012108. http://dx.doi.org/10.1088/1742-6596/1559/1/012108.

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44

Komarek, P. "The impact of fusion on superconducting magnet development in Europe". Fusion Engineering and Design 20 (enero de 1993): 15–22. http://dx.doi.org/10.1016/0920-3796(93)90020-i.

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45

Sas, Jan, Sandra Kauffmann-Weiss y Klaus-Peter Weiss. "EFFECT OF AGING ON MECHANICAL PROPERTIES OF 316LN AT 4.2 K FOR FUSION APPLICATIONS". Acta Metallurgica Slovaca 24, n.º 4 (11 de diciembre de 2018): 287. http://dx.doi.org/10.12776/ams.v24i4.1140.

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<span lang="EN-GB">Within the fusion magnet technology the low-temperature superconductor Nb<sub>3</sub>Sn is usually used for high magnetic field in the range of 12 T and 4.5 K. These superconductors are produced as round strands. Here Nb<sub>3</sub>Sn filaments are embedded in a round copper matrix with a diameter of about 0.8 mm. To allow magnet windings of several Mega-Ampere to produce the needed magnetic field, about 900 superconducting strands are cabled and compacted in a stainless steel conduit resembling the so-called cable-in-conduit-conductor (CICC). However, the mechanically brittle Nb<sub>3</sub>Sn superconducting phase is produced by the diffusion reaction by a long-term heat treatment. Therefore, the magnet winding containing the superconducting strands together with the stainless steel jacket has to undergo this heat treatment. In order to simulate the magnet manufacturing process, seamless tubes were compacted, bend and straightened and tensile stretched by 2.5 % at room temperature followed by the heat treatment necessary for the Nb<sub>3</sub>Sn formation. </span><span>The aim of this study was to compare the microstructures and tensile properties at cryogenic operation temperature of two modified 316LN austenitic stainless steels with very-low carbon (</span><span>≤</span><span lang="EN-GB">0.013</span><span>) in the as built conditions and after heat treatments. Scanning Electron Microscopy (SEM), Electron Backscatter Diffraction (EBSD) and X-ray diffraction were used to study microstructure. Deformation behaviour was investigated by tensile test at 4.2 K.</span>

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46

Barkas, J., Y. Zhai y M. Safabakhsh. "A cryostat for a 6 T conduction-cooled, no-insulation multi-pancake HTS solenoid". IOP Conference Series: Materials Science and Engineering 1240, n.º 1 (1 de mayo de 2022): 012142. http://dx.doi.org/10.1088/1757-899x/1240/1/012142.

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Abstract There is a growing requirement for high-field (>20 T) magnets capable of continuous operation, driven by the needs of both fundamental research and technological advance, particularly in application to an eventual pilot plant for magnetic confinement fusion. Even with HTS windings, such magnets will still require cryogenic cooling, and liquid helium (LHe) immersion, the typical solution to this problem, adds significantly to the operating expenses of such facilities. This reality makes cryogen-free cooling systems a necessity in future high-field magnet systems. The Princeton Plasma Physics Laboratory (PPPL) is exploring conduction-cooling systems of HTS pancake solenoids for a scanning tunneling microscopy (STM) facility at Princeton University, and potentially also for the central solenoid of the Fusion Nuclear Science Facility (FNSF). To these ends, PPPL is designing a cryostat to evaluate the thermal stability of a 5-6 T, 30 double-pancake (DP) REBCO insert coil of 40 mm ID / 70 mm OD, and smaller prototypes, operated in self-field with conduction cooling provided by a 2-stage GM cryocooler. The current design is expected to achieve 1st and 2nd stage temperatures of 44 K and 4-10 K, respectively, with the resistivity of DP-DP solder joints being the principal source of uncertainty in 2nd stage temperature predictions.

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47

Yamafuji, Kaoru. "Superconducting technology for nuclear fusion facilities. Introduction to superconducting magnet technology." Kakuyūgō kenkyū 61, n.º 4 (1989): 229–40. http://dx.doi.org/10.1585/jspf1958.61.229.

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48

Giannini, L., D. Boso, V. Corato, L. Muzzi y A. della Corte. "Engineering the Main Structures of the DEMO Fusion Reactor Magnet System". IEEE Transactions on Applied Superconductivity 32, n.º 6 (septiembre de 2022): 1–5. http://dx.doi.org/10.1109/tasc.2022.3152135.

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Ivanov, D. P., I. O. Anashkin y B. N. Kolbasov. "SUPERCONDUCTING MAGNET SYSTEM FOR RUSSIAN TOKAMAK - FUSION NEUTRON SOURCE DEMO-FNS". Problems of Atomic Science and Technology, Ser. Thermonuclear Fusion 37, n.º 3 (2014): 5–14. http://dx.doi.org/10.21517/0202-3822-2014-37-3-5-14.

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Caspi, S., R. Bangerter, K. Chow, A. Faltens, S. Gourlay, R. Hinkins, R. Gupta et al. "A superconducting quadrupole magnet array for a heavy ion fusion driver". IEEE Transactions on Appiled Superconductivity 9, n.º 2 (junio de 1999): 463–66. http://dx.doi.org/10.1109/77.783335.

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