Bibliographies thématiques / Compact Tokamak

Littérature scientifique sur le sujet « Compact Tokamak »

Auteur : Grafiati
Publié le 14 mars 2023

Créez une référence correcte selon les styles APA, MLA, Chicago, Harvard et plusieurs autres

Choisissez une source :

Sommaire

Consultez les listes thématiques d’articles de revues, de livres, de thèses, de rapports de conférences et d’autres sources académiques sur le sujet « Compact Tokamak ».

À côté de chaque source dans la liste de références il y a un bouton « Ajouter à la bibliographie ». Cliquez sur ce bouton, et nous générerons automatiquement la référence bibliographique pour la source choisie selon votre style de citation préféré : APA, MLA, Harvard, Vancouver, Chicago, etc.

Vous pouvez aussi télécharger le texte intégral de la publication scolaire au format pdf et consulter son résumé en ligne lorsque ces informations sont inclues dans les métadonnées.

Articles de revues sur le sujet "Compact Tokamak"

1

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, no 2141 (4 février 2019) : 20170438. http://dx.doi.org/10.1098/rsta.2017.0438.

Texte intégral
Résumé :
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?’.
Styles APA, Harvard, Vancouver, ISO, etc.
2

Whyte, Dennis. « Small, modular and economically attractive fusion enabled by high temperature superconductors ». Philosophical Transactions of the Royal Society A : Mathematical, Physical and Engineering Sciences 377, no 2141 (4 février 2019) : 20180354. http://dx.doi.org/10.1098/rsta.2018.0354.

Texte intégral
Résumé :
The advantages of high magnetic fields in tokamaks are reviewed, and why they are important in leading to more compact tokamaks. A brief explanation is given of what limits the magnetic field in a tokamak, and why high temperature superconductors (HTSs) are a game changer, not just because of their higher magnetic fields but also for reasons of higher current density and higher operating temperatures. An accelerated pathway to fusion energy is described, defined by the SPARC and ARC tokamak designs. This article is part of a discussion meeting issue ‘Fusion energy using tokamaks: can development be accelerated?’.
Styles APA, Harvard, Vancouver, ISO, etc.
3

Manheimer, Wallace. « Comment on ‘The advanced tokamak path to a compact net electric fusion pilot plant’ ». Nuclear Fusion 62, no 12 (18 octobre 2022) : 128001. http://dx.doi.org/10.1088/1741-4326/ac88e4.

Texte intégral
Résumé :
Abstract This comment (letter) examines a recent GA concept which they hope will lead to a tokamak fusion pilot plant. As tokamaks are now the closest configuration to practical magnetic fusion, if they cannot do a pilot plant, almost certainly no other device can either. The conclusion is that constructing a tokamak fusion pilot plant at this time is enormously risky, and is almost certainly tremendous waste of scarce fusion resources, which could be better used on other efforts in the fusion effort.
Styles APA, Harvard, Vancouver, ISO, etc.
4

Wootton, A. J., J. C. Wiley, P. H. Edmonds et D. W. Ross. « Compact tokamak reactors ». Nuclear Fusion 37, no 7 (juillet 1997) : 927–37. http://dx.doi.org/10.1088/0029-5515/37/7/i02.

Texte intégral
Styles APA, Harvard, Vancouver, ISO, etc.
5

Costley, A. E. « Towards a compact spherical tokamak fusion pilot plant ». Philosophical Transactions of the Royal Society A : Mathematical, Physical and Engineering Sciences 377, no 2141 (4 février 2019) : 20170439. http://dx.doi.org/10.1098/rsta.2017.0439.

Texte intégral
Résumé :
The question of size of a tokamak fusion reactor is central to current fusion research especially with the large device, ITER, under construction and even larger DEMO reactors under initial engineering design. In this paper, the question of size is addressed initially from a physics perspective. It is shown that in addition to size, field and plasma shape are important too, and shape can be a significant factor. For a spherical tokamak (ST), the elongated shape leads to significant reductions in major radius and/or field for comparable fusion performance. Further, it is shown that when the density limit is taken into account, the relationship between fusion power and fusion gain is almost independent of size, implying that relatively small, high performance reactors should be possible. In order to realize a small, high performance fusion module based on the ST, feasible solutions to several key technical challenges must be developed. These are identified and possible design solutions outlined. The results of the physics, technical and engineering studies are integrated using the Tokamak Energy system code, and the results of a scoping study are reviewed. The results indicate that a relatively small ST using high temperature superconductor magnets should be feasible and may provide an alternative, possibly faster, ‘small modular’ route to fusion power. This article is part of a discussion meeting issue ‘Fusion energy using tokamaks: can development be accelerated?’.
Styles APA, Harvard, Vancouver, ISO, etc.
6

Menard, J. E., B. A. Grierson, T. Brown, C. Rana, Y. Zhai, F. M. Poli, R. Maingi, W. Guttenfelder et P. B. Snyder. « Fusion pilot plant performance and the role of a sustained high power density tokamak ». Nuclear Fusion 62, no 3 (7 février 2022) : 036026. http://dx.doi.org/10.1088/1741-4326/ac49aa.

Texte intégral
Résumé :
Abstract Recent U.S. fusion development strategy reports all recommend that the U.S. should pursue innovative science and technology to enable construction of a fusion pilot plant (FPP) that produces net electricity from fusion at low capital cost. Compact tokamaks have been proposed as a means of potentially reducing the capital cost of a FPP. However, compact steady-state tokamak FPPs face the challenge of integrating a high fraction of self-driven current with high core confinement, plasma pressure, and high divertor parallel heat flux. This integration is sufficiently challenging that a dedicated sustained-high-power-density (SHPD) tokamak facility is proposed by the U.S. community as the optimal way to close this integration gap. Performance projections for the steady-state tokamak FPP regime are presented and a preliminary SHPD device with substantial flexibility in lower aspect ratio (A = 2–2.5), shaping, and divertor configuration to narrow gaps to an FPP is described.
Styles APA, Harvard, Vancouver, ISO, etc.
7

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 (4 février 2019) : 20170440. http://dx.doi.org/10.1098/rsta.2017.0440.

Texte intégral
Résumé :
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?’.
Styles APA, Harvard, Vancouver, ISO, etc.
8

Dlougach, Eugenia, Alexander Panasenkov, Boris Kuteev et Arkady Serikov. « Neutral Beam Coupling with Plasma in a Compact Fusion Neutron Source ». Applied Sciences 12, no 17 (23 août 2022) : 8404. http://dx.doi.org/10.3390/app12178404.

Texte intégral
Résumé :
FNS-ST is a fusion neutron source project based on a spherical tokamak (R/a = 0.5 m/0.3 m) with a steady-state neutron generation of ~1018 n/s. Neutral beam injection (NBI) is supposed to maintain steady-state operation, non-inductive current drive and neutron production in FNS-ST plasma. In a low aspect ratio device, the toroidal magnetic field shape is not optimal for fast ions confinement in plasma, and the toroidal effects are more pronounced compared to the conventional tokamak design (with R/a > 2.5). The neutral beam production and the tokamak plasma response to NBI were efficiently modeled by a specialized beam-plasma software package BTR-BTOR, which allowed fast optimization of the neutral beam transport and evolution within the injector unit, as well as the parametric study of NBI induced effects in plasma. The “Lite neutral beam model” (LNB) implements a statistical beam description in 6-dimensional phase space (106–1010 particles), and the beam particle conversions are organized as a data flow pipeline. This parametric study of FNS-ST tokamak is focused on the beam-plasma coupling issue. The main result of the study is a method to achieve steady-state current drive and fusion controllability in beam-driven toroidal plasmas. LNB methods can be also applied to NBI design for conventional tokamaks.
Styles APA, Harvard, Vancouver, ISO, etc.
9

Willis, John W., H. P. Furth, Rodolfo Carrera, Daniel R. Cohn, D. Bruce Montgomery et William F. Weldon. « Compact Tokamak Ignition Concepts ». Journal of Fusion Energy 8, no 1-2 (juin 1989) : 27–41. http://dx.doi.org/10.1007/bf01050775.

Texte intégral
Styles APA, Harvard, Vancouver, ISO, etc.
10

Schmidt, John. « The Compact Ignition Tokamak ». Journal of Fusion Energy 7, no 2-3 (septembre 1988) : 139–42. http://dx.doi.org/10.1007/bf01054633.

Texte intégral
Styles APA, Harvard, Vancouver, ISO, etc.
Plus de sources

Thèses sur le sujet "Compact Tokamak"

1

SEGANTIN, STEFANO. « General assessment and radiation damage minimization of advanced structural materials for compact tokamaks ». Doctoral thesis, Politecnico di Torino, 2022. http://hdl.handle.net/11583/2971115.

Texte intégral
Styles APA, Harvard, Vancouver, ISO, etc.
2

Scipioni, Angel. « Contribution à la théorie des ondelettes : application à la turbulence des plasmas de bord de Tokamak et à la mesure dimensionnelle de cibles ». Thesis, Nancy 1, 2010. http://www.theses.fr/2010NAN10125.

Texte intégral
Résumé :
La nécessaire représentation en échelle du monde nous amène à expliquer pourquoi la théorie des ondelettes en constitue le formalisme le mieux adapté. Ses performances sont comparées à d'autres outils : la méthode des étendues normalisées (R/S) et la méthode par décomposition empirique modale (EMD).La grande diversité des bases analysantes de la théorie des ondelettes nous conduit à proposer une approche à caractère morphologique de l'analyse. L'exposé est organisé en trois parties.Le premier chapitre est dédié aux éléments constitutifs de la théorie des ondelettes. Un lien surprenant est établi entre la notion de récurrence et l'analyse en échelle (polynômes de Daubechies) via le triangle de Pascal. Une expression analytique générale des coefficients des filtres de Daubechies à partir des racines des polynômes est ensuite proposée.Le deuxième chapitre constitue le premier domaine d'application. Il concerne les plasmas de bord des réacteurs de fusion de type tokamak. Nous exposons comment, pour la première fois sur des signaux expérimentaux, le coefficient de Hurst a pu être mesuré à partir d'un estimateur des moindres carrés à ondelettes. Nous détaillons ensuite, à partir de processus de type mouvement brownien fractionnaire (fBm), la manière dont nous avons établi un modèle (de synthèse) original reproduisant parfaitement la statistique mixte fBm et fGn qui caractérise un plasma de bord. Enfin, nous explicitons les raisons nous ayant amené à constater l'absence de lien existant entre des valeurs élevées du coefficient d'Hurst et de supposées longues corrélations.Le troisième chapitre est relatif au second domaine d'application. Il a été l'occasion de mettre en évidence comment le bien-fondé d'une approche morphologique couplée à une analyse en échelle nous ont permis d'extraire l'information relative à la taille, dans un écho rétrodiffusé d'une cible immergée et insonifiée par une onde ultrasonore
The necessary scale-based representation of the world leads us to explain why the wavelet theory is the best suited formalism. Its performances are compared to other tools: R/S analysis and empirical modal decomposition method (EMD). The great diversity of analyzing bases of wavelet theory leads us to propose a morphological approach of the analysis. The study is organized into three parts. The first chapter is dedicated to the constituent elements of wavelet theory. Then we will show the surprising link existing between recurrence concept and scale analysis (Daubechies polynomials) by using Pascal's triangle. A general analytical expression of Daubechies' filter coefficients is then proposed from the polynomial roots. The second chapter is the first application domain. It involves edge plasmas of tokamak fusion reactors. We will describe how, for the first time on experimental signals, the Hurst coefficient has been measured by a wavelet-based estimator. We will detail from fbm-like processes (fractional Brownian motion), how we have established an original model perfectly reproducing fBm and fGn joint statistics that characterizes magnetized plasmas. Finally, we will point out the reasons that show the lack of link between high values of the Hurst coefficient and possible long correlations. The third chapter is dedicated to the second application domain which is relative to the backscattered echo analysis of an immersed target insonified by an ultrasonic plane wave. We will explain how a morphological approach associated to a scale analysis can extract the diameter information
Styles APA, Harvard, Vancouver, ISO, etc.
3

Antl, Marek. « Napájecí soustava s pulsním generátorem pro tokamak COMPASS D ». Master's thesis, Vysoké učení technické v Brně. Fakulta elektrotechniky a komunikačních technologií, 2008. http://www.nusl.cz/ntk/nusl-217596.

Texte intégral
Résumé :
One of the possible ways, how to ensure the necessary electric energy to the future is by the thermonuclear synthesis. Systems that deal with this problem are called stellarator or tokamak. In my work I describe the working principle of the tokamak and its possible future evolution. More precisely I deal with particular tokamak that was brought from Culham to the Prague and its power supply, which became a problem. It is tokamak model COMPASS D. My work consists in power supplying of tokamak reels and power elements in its supply way. However it is just a test gear, which has a long way to the successful end, wich is power supplying instead of power burning. It is just a test gear on which are various tests and analyses carryed out nowadays. Results of these tests will be used for another research and to improve the results of this or other facilities.
Styles APA, Harvard, Vancouver, ISO, etc.
4

Naydenkova, Diana. « Studium plazmatu v zařízeních typu tokamak spektroskopickými metodami ». Doctoral thesis, 2017. http://www.nusl.cz/ntk/nusl-372718.

Texte intégral
Résumé :
In Tokamak department of Institute of Plasma Physics, radiation of high-temperature plasma is investigated using spectroscopic methods in visible, ultraviolet and infrared regions. The radiation gives information regarding tokamak plasma parameters and their changes, which is necessary for future realization of fusion reactor. In the frame of this doctoral thesis the development of spectroscopic diagnostics for observing of plasma radiation and its temporal evolution in COMPASS tokamak was performed. The absolute calibration of developed systems in order to recalculate measured signal to units of radiation was done. The sources of imprecisions of absolute measurements in tokamak conditions are properly discussed in the first part of the dissertation. Plasma radiation in the range 257-1083 nm was measured and interpreted using NIST database and FLYCHK code. Ion density for the most significant impurities was estimated. IDL code for effective ion charge estimation as a ratio of real and hydrogen plasma Bremsstrahlung radiation near 523 nm was developed. Profiles of electron density and temperature measured by Thomson scattering system were used for hydrogen plasma Bremsstrahlung radiation calculations. The example of applying of spectroscopic data for studying of COMPASS plasma heating using neutral beam...
Styles APA, Harvard, Vancouver, ISO, etc.
5

Aftanas, Milan. « Diagnostika Thomsonovým rozptylem na tokamaku COMPASS ». Doctoral thesis, 2015. http://www.nusl.cz/ntk/nusl-349355.

Texte intégral
Résumé :
Thorough study of plasma behaviour in magnetically confined fusion devices is of great importance in recent research. Diagnostics capable to reliably provide important parameters of the hot plasma are key tool in the effort to control fusion energy on Earth. Thomson Scattering diagnostic has a credit of being a complex design diagnostic with reliable measurement of electron temperature and density profiles. The main subjects of this thesis are design of the Thomson Scattering system for the COMPASS tokamak, analysis of output data errors and exploitation of the data to study plasma behaviour. Besides this work, the author has been involved in the design of Thomson Scattering systems for the ITER tokamak and this design is presented here as well. Powered by TCPDF (www.tcpdf.org)
Styles APA, Harvard, Vancouver, ISO, etc.
6

Podolník, Aleš. « Studium sondových diagnostik okrajového plazmatu v tokamaku pomocí počítačových simulací ». Doctoral thesis, 2019. http://www.nusl.cz/ntk/nusl-403911.

Texte intégral
Résumé :
The aim of the thesis is to examine plasma-wall interaction using computer modeling. Tokamak- relevant plasma conditions are simulated using the particle-in-cell model family SPICE working in three or two dimensions. SPICE model was upgraded with a parallel Poisson equation solver and a heat equation solver module. Plasma simulation aimed at synthetic Langmuir probe measurements were performed. First set considered a flush-mounted probe and the effect of variable magnetic field angle was studied with aim to compare existing probe data evaluation techniques and assess their operational space, in which the plasma parameters estimation via fit to the current-voltage characteristic is accurate. Second simulation set studied a protruding probe pin. Effective collecting area of such probe was investigated with intentions of density measurement collection. This area was found to be influenced by a combination of two factors. First, the density dampening inside the magnetic pre-sheath of the probe head, and the second, the extension of the area caused by Larmor rotation. A comparison with experimental results obtained at COMPASS tokamak was was performed, confirming these results. Keywords Langmuir probe, simulation, particle-in-cell, tokamak, Poisson equation, COMPASS 1
Styles APA, Harvard, Vancouver, ISO, etc.

Livres sur le sujet "Compact Tokamak"

1

Dhaba'an, Anees Hameed. Nucleonic design and activation analysis of a high neutron wall loading compact tokamak fusion reactor. Birmingham : University of Birmingham, 1994.

Trouver le texte intégral
Styles APA, Harvard, Vancouver, ISO, etc.
2

Gierszewski, Paul Joseph. Design of the compact toroid fueller for centre fuelling TdeV. Mississauga, Ont : CFFTP, 1992.

Trouver le texte intégral
Styles APA, Harvard, Vancouver, ISO, etc.

Chapitres de livres sur le sujet "Compact Tokamak"

1

Källne, J., P. Batistoni, B. Coppi, R. Dierckx, G. Gorini, M. Martone, L. Perasso et S. Rollet. « Study of Neutron Diagnostics for the Compact Tokamak Ignitor ». Dans Proceedings of the Seventh ASTM-Euratom Symposium on Reactor Dosimetry, 429–36. Dordrecht : Springer Netherlands, 1992. http://dx.doi.org/10.1007/978-94-011-2781-3_50.

Texte intégral
Styles APA, Harvard, Vancouver, ISO, etc.
2

Flanagan, C. A. « OVERVIEW OF THE COMPACT IGNITION TOKAMAK ». Dans Fusion Technology 1986, 375–80. Elsevier, 1986. http://dx.doi.org/10.1016/b978-1-4832-8376-0.50038-3.

Texte intégral
Styles APA, Harvard, Vancouver, ISO, etc.
3

Schmidt, John A. « Ignition with high-field, compact tokamaks ». Dans Fusion Technology 1990, 21–24. Elsevier, 1991. http://dx.doi.org/10.1016/b978-0-444-88508-1.50008-6.

Texte intégral
Styles APA, Harvard, Vancouver, ISO, etc.
4

Vyas, P., A. W. Morris et D. Mustafa. « Analysis of experimental performance and robust stability of vertical position on the COMPASS-D tokamak**This work is jointly funded by the UK DTI, EURATOM and EPSRC (CASE award and grant GR/J06078) ». Dans Fusion Technology 1994, 703–6. Elsevier, 1995. http://dx.doi.org/10.1016/b978-0-444-82220-8.50143-6.

Texte intégral
Styles APA, Harvard, Vancouver, ISO, etc.

Actes de conférences sur le sujet "Compact Tokamak"

1

Sykes, A. « Compact tokamak fusion ». Dans 2015 IEEE 15th International Conference on Environment and Electrical Engineering (EEEIC). IEEE, 2015. http://dx.doi.org/10.1109/eeeic.2015.7165195.

Texte intégral
Styles APA, Harvard, Vancouver, ISO, etc.
2

Stambauch, R. D., G. Bateman, M. G. Bell, D. Cohn, P. Colestock, R. Goldston, S. C. Jardin et al. « The compact ignition tokamak (CIT) ». Dans 1990 Plasma Science IEEE Conference Record - Abstracts. IEEE, 1990. http://dx.doi.org/10.1109/plasma.1990.110576.

Texte intégral
Styles APA, Harvard, Vancouver, ISO, etc.
3

Li, Ge. « Compact Electric Power System for Tokamak ». Dans 2012 IEEE International Power Modulator and High Voltage Conference (IPMHVC). IEEE, 2012. http://dx.doi.org/10.1109/ipmhvc.2012.6518852.

Texte intégral
Styles APA, Harvard, Vancouver, ISO, etc.
4

Stotler, D. P., M. Ulrickson, D. Coster, A. B. Ehrhardt, B. J. Braams et C. F. F. Karney. « Compact ignition tokamak edge and divertor modeling ». Dans 1990 Plasma Science IEEE Conference Record - Abstracts. IEEE, 1990. http://dx.doi.org/10.1109/plasma.1990.110520.

Texte intégral
Styles APA, Harvard, Vancouver, ISO, etc.
5

Martin, F., R. Raman, C. Xiao et J. Thomas. « Compact toroid fuelling of the TdeV tokamak ». Dans International Conference on Plasma Sciences (ICOPS). IEEE, 1993. http://dx.doi.org/10.1109/plasma.1993.593077.

Texte intégral
Styles APA, Harvard, Vancouver, ISO, etc.
6

Mazzucato, E., I. Fidone et R. L. Meyer. « Electron cyclotron heating in the compact ignition tokamak ». Dans AIP Conference Proceedings Volume 159. AIP, 1987. http://dx.doi.org/10.1063/1.36615.

Texte intégral
Styles APA, Harvard, Vancouver, ISO, etc.
7

Ma, C. H., et D. P. Hutchinson. « An infrared interferometer/polarimeter on the compact ignition tokamak ». Dans 1987 Twelth International Conference on Infrared and Millimeter Waves. IEEE, 1987. http://dx.doi.org/10.1109/irmm.1987.9127071.

Texte intégral
Styles APA, Harvard, Vancouver, ISO, etc.
8

Suckewer, S., L. Bromberg et D. Cohn. « Small Scale Tokamak for X-Ray Lithography ». Dans Soft X-Ray Projection Lithography. Washington, D.C. : Optica Publishing Group, 1992. http://dx.doi.org/10.1364/sxray.1992.wb3.

Texte intégral
Résumé :
A toroidal plasma device (tokamak) with electron temperature in the range of 150-200 eV and density ~1013 particles/cm3 can be built as a very compact and relatively inexpensive machine (~3 M$). A tokamak with a major radius R ≈ 1m, minor radius r ≈ 0.1m, and confining magnetic field ~ 5k Gauss is not a very attractive for fusion research, however it can be an excellent source of soft X-ray radiation. In particular if operated in a steady state regime or at a high repetition rate it can provide several orders of magnitude more soft X-ray radiation than a small synchrotron with an undulator. This can be seen easily by comparing the total radiated power of a small tokamak and a small sychrotron, taking into account the spectral intensity distribution of line radiation from the tokamak plasma and of continuum radiation from synchrotron. We will present related calculations. Based on the calculations we will discuss the usefulness of a small tokamak for X-ray projection and proximity lithography and simple methods to change the dominant lines in the plasma radiation spectrum.
Styles APA, Harvard, Vancouver, ISO, etc.
9

Kreischer, K. E., T. L. Grimm, A. W. Mobius et R. J. Temkin. « The Design Of Megawatt Gyrotrons For The Compact Ignition Tokamak ». Dans 13 Intl Conf on Infrared and Millimeter Waves, sous la direction de Richard J. Temkin. SPIE, 1988. http://dx.doi.org/10.1117/12.978393.

Texte intégral
Styles APA, Harvard, Vancouver, ISO, etc.
10

Porkolab, M., P. T. Bonoli, R. Englade, R. C. Myer, G. R. Smith et A. H. Kritz. « Electron cyclotron assisted startup and heating scenarios in the compact ignition tokamak ». Dans Radio−frequency power in plasmas. AIP, 1989. http://dx.doi.org/10.1063/1.38460.

Texte intégral
Styles APA, Harvard, Vancouver, ISO, etc.

Rapports d'organisations sur le sujet "Compact Tokamak"

1

Keeton, D. C. Cooldown of the Compact Ignition Tokamak. Office of Scientific and Technical Information (OSTI), août 1987. http://dx.doi.org/10.2172/5706252.

Texte intégral
Styles APA, Harvard, Vancouver, ISO, etc.
2

Ignat, D. W. Heating the Compact Ignition Tokamak (CIT). Office of Scientific and Technical Information (OSTI), novembre 1989. http://dx.doi.org/10.2172/5344407.

Texte intégral
Styles APA, Harvard, Vancouver, ISO, etc.
3

Wootton, A. J., J. C. Wiley, P. H. Edmonds et D. W. Ross. Compact tokamak reactors. Part 1 (analytic results). Office of Scientific and Technical Information (OSTI), septembre 1996. http://dx.doi.org/10.2172/393331.

Texte intégral
Styles APA, Harvard, Vancouver, ISO, etc.
4

Wiley, J. C., A. J. Wootton et D. W. Ross. Compact tokamak reactors part 2 (numerical results). Office of Scientific and Technical Information (OSTI), octobre 1996. http://dx.doi.org/10.2172/453523.

Texte intégral
Styles APA, Harvard, Vancouver, ISO, etc.
5

Medley, S. S., et K. M. Young. Plasma diagnostics for the compact ignition tokamak. Office of Scientific and Technical Information (OSTI), juin 1988. http://dx.doi.org/10.2172/7231452.

Texte intégral
Styles APA, Harvard, Vancouver, ISO, etc.
6

Post, D., G. Bateman, W. Houlberg, L. Bromberg, D. Cohn, P. Colestock, M. Hughes, D. Ignat, R. Izzo et S. Jardin. Physics aspects of the Compact Ignition Tokamak. Office of Scientific and Technical Information (OSTI), novembre 1986. http://dx.doi.org/10.2172/7056067.

Texte intégral
Styles APA, Harvard, Vancouver, ISO, etc.
7

Singer, C. E., L. P. Ku et G. Bateman. Plasma transport in a compact ignition tokamak. Office of Scientific and Technical Information (OSTI), février 1987. http://dx.doi.org/10.2172/6685807.

Texte intégral
Styles APA, Harvard, Vancouver, ISO, etc.
8

Stotler, D. P., et R. J. Goldston. Ignition probabilities for Compact Ignition Tokamak designs. Office of Scientific and Technical Information (OSTI), septembre 1989. http://dx.doi.org/10.2172/5850300.

Texte intégral
Styles APA, Harvard, Vancouver, ISO, etc.
9

Bateman, G. Delaying sawtooth oscillations in the Compact Ignition Tokamak. Office of Scientific and Technical Information (OSTI), septembre 1986. http://dx.doi.org/10.2172/5068723.

Texte intégral
Styles APA, Harvard, Vancouver, ISO, etc.
10

Stotler, D. P., et N. Pomphrey. Pulse length assessment of compact ignition tokamak designs. Office of Scientific and Technical Information (OSTI), juillet 1989. http://dx.doi.org/10.2172/5892809.

Texte intégral
Styles APA, Harvard, Vancouver, ISO, etc.
Vous pouvez également être intéressé par les bibliographies sur le sujet « Compact Tokamak » pour d’autres types de sources :
Articles de revues
Nous offrons des réductions sur tous les plans premium pour les auteurs dont les œuvres sont incluses dans des sélections littéraires thématiques. Contactez-nous pour obtenir un code promo unique!

Vers la bibliographie