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Artigos de revistas sobre o assunto "Thermonuclear plasmas"

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Rose, S. J., P. W. Hatfield e R. H. H. Scott. "Modelling burning thermonuclear plasma". Philosophical Transactions of the Royal Society A: Mathematical, Physical and Engineering Sciences 378, n.º 2184 (12 de outubro de 2020): 20200014. http://dx.doi.org/10.1098/rsta.2020.0014.

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Considerable progress towards the achievement of thermonuclear burn using inertial confinement fusion has been achieved at the National Ignition Facility in the USA in the last few years. Other drivers, such as the Z-machine at Sandia, are also making progress towards this goal. A burning thermonuclear plasma would provide a unique and extreme plasma environment; in this paper we discuss (a) different theoretical challenges involved in modelling burning plasmas not currently considered, (b) the use of novel machine learning-based methods that might help large facilities reach ignition, and (c) the connections that a burning plasma might have to fundamental physics, including quantum electrodynamics studies, and the replication and exploration of conditions that last occurred in the first few minutes after the Big Bang. This article is part of a discussion meeting issue ‘Prospects for high gain inertial fusion energy (part 1)’.
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Hwang, Eunseok, Dukjae Jang e Myung-Ki Cheoun. "Modification of Thermonuclear Reaction in the Astrophysical Plasma". Communications in Physics 32, n.º 4S (31 de dezembro de 2022): 493. http://dx.doi.org/10.15625/0868-3166/17758.

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Studies on nucleosynthesis enable us to explore the abundance of the chemical elements in our universe. The nucleosynthesis sites are usually assumed to be ideal, the system that the equilibrium statistics and bare Coulomb potential of nuclei are applicable. However, it is still ambiguous whether the astrophysical plasma always stays in the ideal system despite the existence of collision effects and the collective motion of plasma constituents. Hence, we have studied the effects of astrophysical plasma on nuclear astrophysics. In this proceeding, we introduce two phenomena due to the collective motion of astrophysical plasmas. One is the electron screening effect for moving ions, which is referred to as the dynamical screening effect. The other is electromagnetic (EM) fluctuations that lead the EM spectrum to be changed. We present the enhancement for thermonuclear reaction rate due to the dynamical screening effect and change in EM spectrum due to EM fluctuations on astrophysical plasmas. On the basis of those results, we discuss the effects of astrophysical plasmas on thermonuclear reaction rates and changes in solar neutrino fluxes.
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Evans, P. M., A. P. Fews e W. T. Toner. "Diagnosis of laser produced plasmas using fusion reaction products". Laser and Particle Beams 6, n.º 2 (maio de 1988): 353–60. http://dx.doi.org/10.1017/s0263034600004110.

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Experiments have been performed at the Central Laser Facility, Rutherford Appleton Lab., UK. using novel techniques in which laser produced plasmas have been diagnosed by measurements of the charged thermonuclear reaction products. Two types of experiment are being reported here. Firstly, thermonuclear alpha particles from an exploding pusher target have been used to determine the growth of the Rayleigh–Taylor instability in a separate laser driven planar foil. The resulting alpha particle range loss distributions provide a direct measurement of the foil thickness distribution and hence the instability. The R–T instability has been observed in a number of foils with range losses varying between almost zero to over lOμm. Secondly, a thermonuclear particle backlighting technique has been used in the measurement of the stopping power of hot plasma for different materials. The ratio of plasma stopping power to that of the cold material is measured and compared to a value obtained from theoretical modelling. The solid state nuclear track detector CR–39 has been used as a diagnostic for these experiments. A sophisticated image analysis system has been developed to enhance and improve data recovery.
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DEUTSCH, CLAUDE, HRACHYA B. NERSYSIAN e CARLO CERECEDA. "Heavy ion–plasma interaction of IFE concern: Where do we stand now?" Laser and Particle Beams 20, n.º 3 (julho de 2002): 463–66. http://dx.doi.org/10.1017/s0263034602203201.

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Two distinct issues of recent concern for ion–plasma interactions are investigated. First, the subtle connection between quantum and classical ion stopping is clarified by varying the space dimension. Then we evaluate the range of thermonuclear αS′ in dense plasmas simultaneously magnetized and compressed.
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Tsytovich, V. N. "Collective plasma corrections to thermonuclear reaction rates in dense plasmas". Journal of Experimental and Theoretical Physics 94, n.º 5 (maio de 2002): 927–42. http://dx.doi.org/10.1134/1.1484988.

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Wells, Daniel R., Paul Edward Ziajka e Jack L. Tunstall. "Hydrodynamic Confinement of Thermonuclear Plasmas Trisops VIII (Plasma Liner Confinement)". Fusion Technology 9, n.º 1 (janeiro de 1986): 83–96. http://dx.doi.org/10.13182/fst86-a24704.

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Collins, George, e Donald J. Rej. "Plasma Processing of Advanced Materials". MRS Bulletin 21, n.º 8 (agosto de 1996): 26–31. http://dx.doi.org/10.1557/s0883769400035673.

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A plasma, commonly referred to as the “fourth state of matter,” is an ensemble of randomly moving charged particles with a sufficient particle density to remain, on average, electrically neutral. While their scientific study dates from the 19th century, plasmas are ubiquitous, comprising more than 99% of the known material universe. The term “plasma” was first coined in the 1920s by Irving Langmuir at the General Electric Company after the vague resemblance of a filamented glow discharge to a biological plasma.Plasmas are studied for many reasons. Physicists analyze the collective dynamics of ions and electron ensembles, utilizing principals of classical electromagnetics, and fluid and statistical mechanics, to better understand astrophysical, solar, and ionospheric phenomenon, and in applied problems such as thermonuclear fusion. Electrical engineers use plasmas to develop efficient lighting, and high-power electrical switchgear, and for magneto-hydrodynamic (MHD) power conversion. Aerospace engineers apply plasmas for attitude adjustment and electric propulsion of satellites. Chemists, chemical engineers, and materials scientists routinely use plasmas in reactive ion etching and sputter deposition. These methods are commonplace in microelec tronics since they allow synthesis of complex material structures with submicron feature sizes. A substantial portion of the multi-billion-dollar market for tooling used to manufacture semiconductors employs some form of plasma process. When compared with traditional wet-chemistry techniques, these dry processes result in minimal waste generation. Plasmas are also useful in bulk processing—for example as thermal sprays for melting materials.While the quest for controlled thermonuclear fusion dominated much of plasma research in the 1960s and 1970s, in the last 20 years it has been the application of plasmas to materials processing that has provided new challenges for many plasma practitioners. It is not surprising that the guest editors and several of the authors for this issue of MRS Bulletin come from a fusion plasma-physics background.
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Rebhan, Eckhard R., e Guido Van Oost. "Thermonuclear Burn Criteria for D-T Plasmas". Fusion Science and Technology 49, n.º 2T (fevereiro de 2006): 16–26. http://dx.doi.org/10.13182/fst06-a1100.

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Tsytovich, V. N., e M. Bornatici. "Rates of thermonuclear reactions in dense plasmas". Plasma Physics Reports 26, n.º 10 (outubro de 2000): 840–67. http://dx.doi.org/10.1134/1.1316825.

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Anderson, D., H. Hamnen, M. Lisak, T. Elevant e H. Persson. "Transition to thermonuclear burn in fusion plasmas". Plasma Physics and Controlled Fusion 33, n.º 10 (1 de setembro de 1991): 1145–59. http://dx.doi.org/10.1088/0741-3335/33/10/003.

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Teses / dissertações sobre o assunto "Thermonuclear plasmas"

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Chaniotakis, E. A. (Emmanouil A. ). "Ignition and burn control characteristics of thermonuclear plasmas". Thesis, Massachusetts Institute of Technology, 1990. http://hdl.handle.net/1721.1/13659.

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Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1990.
Includes bibliographical references (leaves 232-238).
by Emmanouil Antony Chaniotakis.
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1990.
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BONANOMI, NICOLA. "Experimental investigation and gyro-kinetic modelling of turbulent transport in thermonuclear plasmas". Doctoral thesis, Università degli Studi di Milano-Bicocca, 2018. http://hdl.handle.net/10281/198976.

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ITER (International Thermonuclear Experimental Reactor) rappresenterà un passo fondamentale per la realizzazione della fusione termonucleare controllata. Tra i problemi ancora aperti, il controllo del trasporto turbolento è cruciale per ITER, che richiederà alti valori di temperatura, densità e confinamento del plasma. Questo lavoro si focalizza su quattro aspetti riguardanti il trasporto di calore turbolento nel centro del plasma: l'effetto delle impurezze leggere, l'effetto delle particelle veloci, il ruolo delle instabilità su scala elettronica e delle interazioni multi-scala e l'effetto della massa della specie ionica principale del plasma (effetto isotopico). L'esecuzione e l'analisi di esperimenti in plasmi in L-mode nel tokamak JET è affiancata dall'uso di simulazioni giro-cinetiche con il codice GENE e da test dei modelli quasi-lineari TGLF e QuaLiKiz, usati per la predizione di plasmi di ITER. Il trasporto turbolento è principalmente dovuto a instabilità su scale dell'ordine del raggio di Larmor ionico ed elettronico causate dai gradienti della temperatura ionica ed elettronica oltre una soglia in tali gradienti. Sopra tale soglia, il flusso turbolento cresce con un tasso che determina quanto le temperature sono rigide rispetto a un incremento della potenza di riscaldamento. Soglia e livello di rigidità sono usate in questa tesi per caratterizzare lo stato turbolento del plasma in diverse condizioni. Sono misurate sperimentalmente e comparate con le predizioni numeriche per una validazione dei modelli utilizzati. Le instabilità su scala elettronica sono state trovate fondamentali per spiegare il flusso di calore elettronico sperimentale. Una forte interazione tra scale ioniche ed elettroniche è stata osservata, i modi su scala elettronica essendo più forti quando i modi su scala ionica sono vicini alla stabilità, come sarà in ITER. TGLF è in buon accordo con le simulazioni giro-cinetiche ed è adatto per predizioni qualitative di questi effetti in scenari futuri. Riguardo alle impurezze leggere, le densità di 3He,Be,C,N e Ne e hanno differenti profili radiali negli stessi plasmi, mentre le simulazioni predicono lo stesso profilo per tutte le impurezze. Plasmi in cui N è stato iniettato hanno gradienti di Ti più alti, ben riprodotti e spiegati dalle simulazioni giro-cinetiche. TGLF e QuaLiKiz hanno punti di disaccordo con le simulazioni giro-cinetiche. Indicazioni sui miglioramenti necessari sono state fornite. Una prima prova sperimentale di una forte stabilizzazione del trasporto di calore dovuta alle particelle veloci è stata ottenuta in plasmi con bassa rotazione. Le simulazioni giro-cinetiche indicano due principali meccanismi di stabilizzazione. Uno elettrostatico legato a interazioni risonanti onde-particelle veloci, uno elettromagnetico e sensibile alla pressione del plasma. Anche la funzione di distribuzione delle particelle veloci è determinante. Questi meccanismi non sono ancora stati introdotti nei modelli quasi-lineari. Infine, plasmi di deuterio sono stati comparati con plasmi di idrogeno con simili parametri. Te e Te sono più basse in plasmi di idrogeno e le differenze partono dal bordo del plasma. Nessuna differenza sostanziale è stata osservata nel trasporto di calore a bassa potenza, ma ad alta potenza, quando le particelle veloci sono importanti, il loro effetto di stabilizzazione è minore in plasmi di idrogeno. Una spiegazione è stata trovata nella diversa pressione delle particelle veloci, che in H è la metà di quella in D , a causa di diverse configurazioni dei sistemi di riscaldamento. In conclusione, differenti aspetti del trasporto di calore turbolento sono stati studiati in plasmi L-mode del JET. Un'interpretazione dei risultati sperimentali è stata ottenuta con l'aiuto di simulazioni giro-cinetiche, e alcuni effetti fisici rilevanti per ITER sono stati identificati. Indicazioni sulla validità e su possibili miglioramenti dei modelli utilizzati sono state ottenute.
ITER (International Thermonuclear Experimental Reactor) will represent a fundamental step in the realization of controlled thermonuclear fusion. Among the problems still open, the understanding of the turbulent transport in the plasma is crucial for ITER, that will require high plasma temperature, density and confinement. This work focuses on four topics related to the thermal transport in a tokamak plasma core: the effects of light impurities, the effects of fast particles, the role of electron scale turbulence and multi-scale interactions and the effects of the plasma main ion mass (isotope effect). It covers the execution and analysis of experiments in JET tokamak L-mode plasmas, the use of local gyro-kinetic simulations (using the GENE code) to model the plasma and the test of the quasi-linear models TGLF and QuaLiKiz, used for ITER predictions. The turbulent transport in a tokamak is mainly due to instabilities on scales of the order of ion or electron Larmor radius driven by the ion and electron temperature gradients over a threshold in these gradients. Above the threshold, the turbulent flux increases with a rate that determines how stiff the temperature profiles are against an increase of heating power. Threshold and stiffness are key concepts used in this thesis to characterize the turbulent state of plasmas in different conditions. They are measured experimentally and compared to the theoretical predictions, providing a deeper insight into the plasma behavior and a stringent validation procedure for the models. Electron scale modes have been found determinant to explain the experimental electron heat flux and stiffness. A strong interaction between ion and electron scales was also found, with electron modes being strongest in conditions where ion scale modes are marginal stable, as will be the case in ITER. The TGLF model is in good agreement with the multi-scale gyro-kinetic simulations and can therefore be suitable for at least a qualitative exploration of these effects in future scenarios. Regarding the light impurities, the density profiles of 3He,Be,C,N and Ne show different peaking in the same plasmas, whilst theory predicts similar peaking for all the impurities. Discharges with N injection show higher peaking of Ti, well explained and reproduced by gyro-kinetic simulations. TGLF and QuaLiKiz show several discrepancies with the gyro-kinetic simulations. Indications have been provided on the improvements needed. A first experimental evidence of a strong thermal transport stabilization due to fast ions has been obtained in plasmas with low rotation. Gyro-kinetic simulations indicate two main stabilization mechanisms. One is electrostatic and related to a resonant wave-fast particle interaction, one is electromagnetic and sensitive to the total plasma pressure. The fast ion distribution function has also an influence on the level of the stabilization. These mechanisms are still not included in the quasilinear models. Finally, D plasmas have been compared to H plasmas with similar operational settings. Te and Ti are lower in H plasmas, the difference starting at the plasma edge. No substantial differences have been observed in the thermal transport in the plasma core at low power, but at high power, when fast ions are important, their stabilization effects appear less strong in H plasmas. An explanation has been found in the differences between the fast ion populations, with H plasmas featuring ~1/2 of the fast ion pressure in D, due to the different parameters of the heating systems. In conclusion, different aspects of thermal turbulent transport have been studied in JET L-mode plasmas. An interpretation of the experimental results has been reached with the help of gyro-kinetic simulations, and some physical effects have been evidenced to be relevant for future ITER scenarios. Some important indications on the validity and on possible improvements of the available numerical models have been obtained.
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Auriemma, Fulvio. "Particle transport in Reversed Field Pinch plasmas". Doctoral thesis, Università degli studi di Padova, 2008. http://hdl.handle.net/11577/3425154.

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This thesis is aimed at studying the transport of particles in magnetically confined thermonuclear plasma. The understanding of the transport properties in devices for fusion plasmas is one of the key factor to keep the correct operating conditions in a future fusion reactor. Indeed one of the open issues in magnetic fusion studies, which prevents the realization of an efficient thermonuclear reactor, is the high level of energy and particle transport in the direction perpendicular to the confining magnetic field. This phenomenon reduces confinement properties and has to be solved in order to obtain energy from thermonuclear fusion processes. The amount of particle and energy transport experimentally observed cannot be interpreted in the framework of the classical theory. Understanding the underlying physics of this anomalous transport remains the outstanding critical physical issue in fusion research. Nowadays it is generally accepted that anomalous transport is partially due to magnetic chaos owing to the magnetic perturbations of the equilibrium magnetic fields. The Reversed Field Pinch (RFP) configuration, with its wide spectrum of magnetic perturbations, offers a suitable testbed to verify the theory and to reveal the inner mechanism underlying the transport in fusion magnetic devices. The magnetic perturbations, also dubbed dynamo or MagnetoHydroDynamic (MHD) modes, sustain the RFP configuration against the resistive magnetic diffusion. Unfortunately they have global negative effects: as already stated they lead to the stochastization of the equilibrium magnetic field over a large part of the plasma core and moreover their phase locking generates an interference pattern that results in a global distortion of the plasma column: the so-called Locked Mode (LM) that has its maximum effect at a well defined toroidal position. Many techniques have been tested with the aim of reducing the MHD modes. The most effective are the Pulsed Poloidal Current Drive (PPCD) that modifies the internal current profile and the active control of the radial field at the edge by means of a system of active coils, the so-called Virtual Shell (VS). All the transport mechanisms acting inside the plasma modify the shape of the density profile. The density is measured by means of interferometer: a non-perturbative diagnostic that utilizes electromagnetic waves to probe the plasma. A part of this thesis will be addressed to determine the global particle diffusion coefficients in relation to the magnetic perturbations amplitude. This analysis has been carried on TPE-RX device: a large RFP machine sited in Tsukuba (Jp). In order to study the global confinement properties, the transport analysis has been carried out analyzing data collected far from to the LM, where its local effect could be neglected. A transport code (in our case TED, acronym of TEmperature and Density) computes the density profile according to transport parameters supplied by the user. The computed profile is compared to the experimental one, determining the correctness of the model assumed to provide the transport coefficients. With this analysis it has been confirmed that damping the MHD modes amplitude by means of the PPCD the particle confinement globally improves and the diffusion coefficient is strongly reduced in the central zone of the plasma. This result has been further confirmed by the density behaviour during pellet injection experiments, where the particles released by the pellet in PPCD discharges are better confined inside the plasma than in plasmas with standard magnetic perturbations. The dynamo modes, as already stated, generate a global distortion of the Last Close Flux Surface (LCFS) of the plasma: the LM. The plasma cross section results shrunk in a wide toroidal region of about 100° and bulging in another region of the similar toroidal range. Moreover an helical distortion of the column with magnetic lines that directly hit the wall is present. The VS system installed at RFX-mod (the largest RFP device in the world with design maximum plasma current of 2 MA, located in Padova) provides an important reduction of the helical perturbation but is less effective on healing the shrinking of the LCFS, highlighting for the first time its effects on plasma confinement. The two toroidal regions with different cross section have been characterized studying the density profile, the density fluctuations and the magnetic fluctuations: the shrunk region shows an improved transport, providing the first experimental evidence of toroidal asymmetric confinement properties in an RFP plasma. Moreover the RFX-mod pulses are affected by spontaneous reorganization of the internal current and magnetic profiles, the so-called Dynamo Relaxation Events (DREs). The density behaviour and the magnetic topology during the DREs have been analyzed, confirming the different nature of the shrunk and the bulging region of the plasma.
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Commaux, Nicolas. "Contrôle du profil de densité dans le plasma de Tore Supra : comparaison de différentes méthodes d'alimentation en particules". Paris 11, 2007. http://www.theses.fr/2007PA112207.

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Le comportement d’un plasma de réacteur en fonction de la méthode utilisée pour l’alimenter en particules est difficile à prévoir. Le travail présente ici a été réalisé sur Tore Supra. 2 sujets ont été étudiés : la comparaison du comportement d’un plasma a forte fraction de la densité de Greenwald selon la manière dont il est alimenté et l’étude de l’homogénéisation de la matière déposée par un glaçon (mode d’alimentation prévu pour ITER). Les expériences à forte fraction de Greenwald effectuées sur Tore Supra ont montré que le comportement du plasma dépend de la méthode d'alimentation. Le confinement de l'énergie avec les glaçons est en accord avec les prévisions établies. Ce comportement est moins favorable pour une alimentation par injection supersonique ou classique car une perte de confinement est ici observée. Ce phénomène n'est pas lié au transport mais à la position du dépôt de matière (au bord pour le gaz et au coeur pour les glaçons). Le travail concernant l'homogénéisation de la matière déposée par une injection de glaçon a pour but d'étudier le mouvement de dérive éjectant la matière déposée vers le côté faible champ. Un nouveau phénomène a été mis en évidence : l'influence des surfaces magnétiques à facteur de sécurité (q) entier. Quand la matière dérivant vers le côté faible champ traverse une telle surface, elle subit un phénomène qui arrête la dérive. Ce travail montre aussi que le mouvement de dérive suivant une injection de glaçon côté fort champ est négligeable sur Tore Supra. Cette étude confirme que l'alimentation par injection de glaçons sera un moyen essentiel d'alimentation pour ITER et que l'injection côté faible champ pourrait être reconsidéré
The behaviour of a reactor-class plasma when fuelled using the existing techniques is difficult to foresee. The present work has been initiated on Tore Supra. Two topics have been studied: the comparison of the plasma behaviour when fuelled using the different techniques at high Greenwald density fractions and the study of the homogenisation following a pellet injection (fuelling technique for ITER burning plasmas). The experiments at high Greenwald density fractions performed on Tore Supra showed that the plasma behaviour is dependent on the fuelling method. The plasma energy confinement is following the scaling laws determined at low density when fuelled using pellet injection, which is better than for gas puffing and supersonic injection, both inducing a significant confinement loss. This behaviour is not related to transport but to the position of the matter source (at the edge for gas and close to the centre for pellets). The study concerning the homogenisation phenomena following a pellet injection aims to study the drift effect that expels the mater deposited toward the low field side. A new phenomenon was discovered: the influence of magnetic surfaces with an integer-valued safety factor (q). When the mater drifting toward low field side crosses an integer q surface, it experiences an effect that stops the drift motion. This study allows also determining that the drift following a pellet high field side injection appears negligible in Tore Supra. This work confirms that the pellet injection is an important tool for ITER plasma fuelling and that the low field side injection scheme should not be totally withdrawn for fuelling
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Ballabio, Luigi. "Calculation and Measurement of the Neutron Emission Spectrum due to Thermonuclear and Higher-Order Reactions in Tokamak Plasmas". Doctoral thesis, Uppsala : Acta Universitatis Upsaliensis : Univ.-bibl. [distributör], 2003. http://publications.uu.se/theses/91-554-5512-3/.

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NOCENTE, MASSIMO. "Neutron and gamma-ray emission spectroscopy as fast ion diagnostics in fusion plasmas". Doctoral thesis, Università degli Studi di Milano-Bicocca, 2012. http://hdl.handle.net/10281/28397.

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This thesis work addresses neutron and γ-ray emission spectroscopy as fast ion diagnostics for fusion plasmas. Two main topics are considered. The first one is the determination of the fast ion energy distribution from measured neutron and γ-ray emission spectra. Neutron spectroscopy has been used at the JET tokamak since 1984. Advanced spectrometers have been built and several features of the neutron emission spectrum have been measured and interpreted in terms of the reaction kinematics. This thesis adds to this knowledge base by inspecting the role of nuclear elastic scattering in producing high energy components in the spectrum from fusion neutrons. The analysis focuses on the possibility to determine the energy distribution tail temperature of radio- frequency heated 3He ions in deuterium plasmas with an admixture of 3He. The RF generation of fast 3He ions is described and the knock-on components are determined with the help of newly derived 3He +d scattering cross sections. Results are presented on the neutron emission spectrum and its contributions from different deuteron velocity components. It is shown that knock-on leaves an observable feature in the spectrum with a clear dependence on absorbed RF power. The investigation is then generalized to D, (3He)D, DT and (3He)DT plasmas, where the relative magnitude of nuclear elastic scattering from different fusion products is determined. The resulting signatures in the neutron emission spectrum are calculated and their relevance for fast ions diagnosis in a burning plasma experiment is discussed. Gamma-ray spectroscopy is a relatively new technique compared to neutron spectroscopy. The Doppler broadening of characteristic γ-ray emission peaks from 12C(3He, pγ)14N reactions in fusion plasmas was measured for the first time in 2008 at the JET tokamak thanks to the installation of a High Purity Germanium detector. In this thesis, intensities and detailed spectral shapes of γ-ray emission peaks are successfully reproduced using a physics model combining the kinetics of the reacting ions with a detailed description of the nuclear reaction differential cross sections for populating the L1-L8 14N excitation levels yielding the observed γ-ray emission. A Monte Carlo code, named GENESIS, was written for the purpose of interpreting γ-ray emission from fusion plasmas and is used here to determine the tail temperature of fast 3He ions from the observed peak shapes. Experiments performed in 4He plasmas of the JET tokamak are also presented. 4He ions were accelerated to the MeV range by coupling third harmonic radio frequency heating to an injected 4He beam. For the first time, Doppler broadening of γ-ray peaks from the 12C(d, pγ)13 C and 9Be(α, nγ)12 C reactions was observed and is here interpreted with the GENESIS code. Acceleration of 4He particles at energies as high as 6 MeV is demonstrated; implications of these results for α particle observations through γ-ray emission spectroscopy in next step deuterium-tritium plasmas are discussed. A second topic addressed by this work is the study of fast ion driven instabilities through γ-ray emission spectroscopy, with emphasis on the development of instrumentation. A high efficiency, high resolution, fast γ-ray spectrometer based on the LaBr3 scintillator and designed for measurements in the MHz range was developed and is here presented. An algorithm based on pulse shape fitting was written to reconstruct γ-ray spectra from digitized data and is shown to provide an energy resolution equivalent to a traditional analog spectrometry chain at low counting rates. The same system was used to perform γ-ray spectroscopy in the MHz range, as demonstrated in experiments performed at nuclear accelerators. γ-ray emission spectra at rates as high as 4 MHz from p + 27Al reactions collected at the Tandem Van der Graaf accelerator of the Nuclear Institute “Horia Hulubei“ (Magurele, RO) are presented and show little or no degradation of the energy resolution. The developed system was also employed to study instabilities driven by fast protons in the ASDEX Upgrade tokamak. The observed γ-ray emission level induced by energetic protons is used to determine an effective tail temperature of the proton distribution function that can be compared with Neutral Particle Analyzer measurements. More generally the measured emission rate is used to assess the confinement of protons with energies less than 400 keV in discharges affected by Toroidal Alfven Eigenmode instabilities. The derived information on confined ions is combined with observations made with the ASDEX Upgrade Fast Ion Loss Detector. The results presented in this thesis represent a step forward in the development of nuclear radiation based methods for burning plasma diagnostics. In particular, they demonstrate that quantitative information on the energy distribution of fast ions and their interaction with plasma instabilities can be inferred from neutron and γ-ray mea- surements by taking into account in detail the reaction processes contributing to the emission of nuclear radiation from the plasma.
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Fonseca, António Manuel Marques. "Alguns Aspectos do Desempenho do Tokamak TCABR: Modelamento, Simulações e Resultados Experimentais". Universidade de São Paulo, 2000. http://www.teses.usp.br/teses/disponiveis/43/43131/tde-30082006-121405/.

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Neste trabalho são abordados alguns aspectos do tokamak TCABR, particularmente no que diz respeito à ruptura do plasma, às descargas e ao sistema vertical. Desenvolveu-se um modelo zero-dimensional para modelagem das descargas, envolvendo 5 equações diferenciais. Com esse modelo obteve-se os perfis temporais de parâmetros importantes da descarga tais como: corrente de plasma, tensão de enlace, temperatura eletrônica, densidade eletrônica e densidade de partículas neutras. Verificou-se, com as simulações, a influência de parâmetros importantes no comportamento das descargas. A partir de resultados experimentais do TCA e do TCABR verificou-se a compatibilidade desses resultados com o modelo. Fez-se um estudo da ruptura do plasma no TCABR utilizando-se um modelo físico para os processos que envolvem a ruptura com o qual pode-se delimitar a região de ruptura que depois pode ser comparada com os resultados experimentais. Experimentalmente verificou-se que, para o TCABR, a ruptura ocorre para pressões entre 9.10-6 a 3.10-4 mbar e campos elétricos entre 2 e 10 V/m. A relação campo-pressão, E/p, na região de ruptura, está entre 3.107 e 5.108 V.m-1.bar-1. Foi também feito um estudo do sistema de controle realimentado do campo vertical onde determinou-se algumas funções de transferências importantes, particularmente para os blocos não lineares desse sistema. A partir de um programa computacional foi feito um mapeamento do campo vertical e do índice de curvatura do campo. Verificou-se que a razão entre a componente vertical do campo, no centro do vaso, e o valor correspondente de corrente que passa pelas espiras é de 3,5.10-5 T/A e o índice de curvatura do campo está em torno de 0,45.
In this work, some aspects of the TCABR tokamak are studied. In particular, some points concerned to the plasma breakdown, to discharge characteristics in tokamak mode and to the vertical field system are investigated. A zero-dimensional model has been developed, especially for this work, based on five differential equations involving the ohmic heating circuit and the conservation laws of energy, electrical charge and neutral particles. The model was used for simulating the TCABR plasma discharges. Therefore, time profiles of important plasma parameters like plasma current, loop voltage, electron temperature, electron density and neutral density, were obtained. Also, as a result of the simulations, was verified how the tokamak machine parameters and plasma parameters influence the behavior of the discharges. Some experimental results from the TCABR and TCA were compared with the results of the simulations. A study of the rupture of the plasma was carried out adopting a physical model that includes many physical processes. This model was used to delimit the breakdown region for TCABR tokamak machine and as a tool to understand the experimental data. Experimentally, it was observed that, for TCABR, the rupture occurs for pressures values between 1.10-5 to 3.10-4 mbar, and electric fields values between 2 and 10 V/m. The ratio electric field-pressure (E/p), in the rupture region, is between 3.107 and 5.108 V.m-1.bar-1. For the control system of the vertical field we obtained some transfer functions mainly for the non-linear blocks of the system that have been used in the experimental tests. A computer program was developed to obtain the map of the magnetic vertical field lines and the index of curvature of the field. Finally it was verified that, in the center of the vessel, the ratio between the magnetic vertical field to the electric current that flows in the vertical coils is, 3.5.10-5 T/A and the index of curvature of the field is ~0.45.
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Mukhtar, Qaisar. "On Monte Carlo Operators for Studying Collisional Relaxation in Toroidal Plasmas". Doctoral thesis, KTH, Fusionsplasmafysik, 2013. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-120590.

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This thesis concerns modelling of Coulomb collisions in toroidal plasma with Monte Carlo operators, which is important for many applications such as heating, current drive and collisional transport in fusion plasmas. Collisions relax the distribution functions towards local isotropic ones and transfer power to the background species when they are perturbed e.g. by wave-particle interactions or injected beams. The evolution of the distribution function in phase space, due to the Coulomb scattering on background ions and electrons and the interaction with RF waves, can be obtained by solving a Fokker-Planck equation.The coupling between spatial and velocity coordinates in toroidal plasmas correlates the spatial diffusion with the pitch angle scattering by Coulomb collisions. In many applications the diffusion coefficients go to zero at the boundaries or in a part of the domain, which makes the SDE singular. To solve such SDEs or equivalent diffusion equations with Monte Carlo methods, we have proposed a new method, the hybrid method, as well as an adaptive method, which selects locally the faster method from the drift and diffusion coefficients. The proposed methods significantly reduce the computational efforts and improves the convergence. The radial diffusion changes rapidly when crossing the trapped-passing boundary creating a boundary layer. To solve this problem two methods are proposed. The first one is to use a non-standard drift term in the Monte Carlo equation. The second is to symmetrize the flux across the trapped passing boundary. Because of the coupling between the spatial and velocity coordinates drift terms associated with radial gradients in density, temperature and fraction of the trapped particles appear. In addition an extra drift term has been included to relax the density profile to a prescribed one. A simplified RF-operator in combination with the collision operator has been used to study the relaxation of a heated distribution function. Due to RF-heating the density of thermal ions is reduced by the formation of a high-energy tail in the distribution function. The Coulomb collisions tries to restore the density profile and thus generates an inward diffusion of thermal ions that results in a peaking of the total density profile of resonant ions.

QC 20130415

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Monnier, Arnaud. "Interactions entre perturbations magnétiques macroscopiques et turbulence microscopique dans un modèle 3D d'un plasma de tokamak". Thesis, Aix-Marseille, 2013. http://www.theses.fr/2013AIXM4773/document.

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Cette thèse porte sur l'interaction entre un plasma de bord de tokamak et une perturbation magnétique résonante (RMP), utilisée principalement pour le contrôle de phénomènes de relaxations quasi-périodiques, présents dans un régime de confinement amélioré. Il permet notamment d'atteindre des conditions favorables aux réactions de fusion nucléaire. Il a été observé que la présence de perturbations magnétiques modifie la topologie magnétique au bord ce qui engendre une diminution de l'amplitude des relaxations, voire leur suppression. De précédents travaux ont étudié l'effet de perturbations magnétiques sur un plasma relaxant via des simulations numériques. Le modèle utilisé était dans un cas électrostatique, c'est à dire que la topologie magnétique n'évoluait pas dans le temps. Dans cette thèse, l'étude est faite dans un modèle de plasma de bord prenant en compte les fluctuations magnétiques via le code numérique EMEDGE3D. Ce code a été modifié pour pouvoir imposer une perturbation magnétique résonante. Des vérifications par des modèles réduits ont été menées sur la pénétration d'une perturbation magnétique ainsi que sur l'effet d'une vitesse cisaillée sur la pénétration. Ensuite, un RMP a été imposé dans un plasma non turbulent avec et sans vitesse cisaillée. Un phénomène d'écrantage, empêchant la pénétration d'une perturbation, a été identifié analytiquement et observé dans les simulations. Cette étude a été réitérée dans un plasma turbulent, et aussi en présence d'une barrière (vitesse cisaillée). Le plasma turbulent engendre une amplification du RMP, tandis que la barrière est affectée par la présence de cellules de convection fixes générées par la perturbation
In this thesis, the interaction between tokamak edge plasma and resonant magnetic perturbation (RMPs) is studied. It is mainly used to mitigate quasi-periodic relaxations in enhanced confinement regime. This regime allows to obtain good conditions for nuclear fusion. Introduction of a RMP in a tokamak plasma has been observed to modified the magnetic topology at the edge and decrease the relaxation amplitude up to complete suppression. Previous works studied the RMP effect on a plasma with relaxations, via numerical simulations. The model used for that consider the electrostatic approximation, where the magnetic topology does not evolve in time. In this thesis, the study is done with an edge plasma model taking into account magnetic fluctuations via the numerical code EMEDGE3D. This code has been modified to include the resonant magnetic perturbation. Comparison with reduced models has been carried out on the RMP penetration and the effect of sheared velocity on it. Then a RMP has been induced in a stable plasma, with or without imposed sheared rotation. A condition on the sheared velocity has been identified to avoid the screening effect, that would prevent the RMP penetration, analytically and in numerical simulations. This works has been repeated in a turbulent plasma in presence or not of transport barrier (sheared velocity). The turbulent plasma generate an effective RMP amplification, while the transport barrier is affected by locked convective cells due to the RMP
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El, Messoudi Abdelmalek. "Modélisation des détonations thermonucléaires en plasmas stellaires dégénérés: applications aux supernovae de types Ia". Doctoral thesis, Universite Libre de Bruxelles, 2008. http://hdl.handle.net/2013/ULB-DIPOT:oai:dipot.ulb.ac.be:2013/210461.

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Plusieurs évènements astrophysiques comme les novae, les supernovae de type Ia (SNeIa) et les sursauts X sont le résultat d'une combustion thermonucléaire explosive dans un plasma stellaire. Les supernovae comptent parmi les objets astrophysiques les plus fascinants tant sur le plan théorique que sur celui des observations. Au moment de l'explosion, la luminosité d'une supernova peut égaler celle de l'intégralité des autres étoiles de la galaxie. On admet aujourd’hui que les SNeIa résultent de l'explosion thermonucléaire d'une étoile naine blanche, un objet dense et compact composé de carbone et d'oxygène. Divers chemins évolutifs peuvent conduire à l’explosion de la naine blanche si celle-ci est membre d’un système stellaire binaire. Néanmoins, la nature du système binaire, les mécanismes d'amorçage et de propagation de la combustion thermonucléaire ainsi que le rapport carbone/oxygène au sein de l'étoile compacte ne sont pas encore clairement identifiés à ce jour. En ce qui concerne l’écoulement réactif, on invoque ainsi une détonation (Modèle sub-Chandrasekhar), une déflagration ou la transition d'une déflagration vers une détonation (Modèle Chandrasekhar). La détonation semble donc jouer un rôle prépondérant dans l'explication des SNeIa.

Les difficultés de modélisation des détonations proviennent essentiellement (i) de la libération d'énergie en plusieurs étapes, de l’apparition d’échelles de temps et de longueurs caractéristiques très différentes (ii) des inhomogénéités de densité, de température et de composition du milieu dans lequel se propage le front réactif et qui donnent naissance aux structures cellulaires et autres instabilités de propagation du front (extinctions et réamorçages locaux).

En plus de celles citées ci-dessus, deux autres difficultés majeures inhérentes à l'étude de ce mode de propagation dans les plasmas stellaires sont rencontrées :la complexité de l’équation d’état astrophysique et la cinétique nucléaire pouvant impliquer plusieurs milliers de nucléides couplés par plusieurs milliers de réactions. Ainsi, les premiers travaux impliquant une combustion thermonucléaire explosive ont été réalisés sur bases d'hypothèses simplificatrices comme l'équilibre nucléaire statistique instantané des produits de réactions ou l'utilisation d'un réseau réduit à une dizaine d'espèces nucléaires. Dans tous ces travaux, la détonation est assimilée à une discontinuité totalement réactive (détonation de Chapman-Jouguet ou CJ). La résolution de l'onde de détonation nécessite l'étude détaillée du processus nucléaire se déroulant dans la zone de réaction. Malheureusement, les supports de calculs actuels ne permettent pas encore ce type de simulations pour les détonations astrophysiques. Le modèle ZND qui constitue une description unidimensionnelle stationnaire de l’écoulement (plan ou courbé) constitue une excellente approximation de la réalité.

Notre travail réexamine les résultats des calculs des structures des ondes de détonations stellaires dans les conditions de température, de densité et de composition envisagées dans les travaux de ce type (détonation CJ et ZND) réalisés jusqu’à présent mais avec une équation d’état appropriée aux plasmas stellaires et une cinétique nucléaire nettement plus riche ;le plus grand réseau jamais utilisé pour ce genre d’études (333 noyaux couplés par 3262 réactions), prenant en compte les données les plus récentes de la physique nucléaire (vitesses de réaction et fonctions de partition)./Several astrophysics events like novae, supernovae and X burts, result from an explosive thermonuclear burning in stellar plasma. Type Ia Supernovae (SNeIa) count amoung the most fascinating stellar objects, they can be more brighter than an entire galaxy. Astrophysic works show that SNeIa may result from a thermonuclear explosion of a compact and dense star called carbon-oxygen white dwarf. The ignition stage and the propagation mode of the thermonuclear combustion wave are not identified yet. The Deflagration-to-Detonation Transition process (or "delayed detonation") sims to give the best overall agrements with the observations :detonations can play appart in SNeIa events.

Simulating thermonuclear detonations count same difficults. The most important are the burning length scales that spent over more than ten oders of magnitud, the nuclear kinetics that involve thousands of nuclids linked by thousands of nuclear reactions and the stellar plasma equation of state (EOS). Hydrodynamical simulations of detonation use very simplified ingedients like reduced reactions network and asymptotic EOS of completely electron degenerate stellar plasma.

Our work is the modelling of these detonations using more representative EOS of the stallar plasma that includs ions, electrons, radiation and electron-pistron pairs. We also use a more

detailed kinetic network, comprising 331 nuclids linked by 3262 capture and photodisintegration reactions, than those usualy employed.


Doctorat en Sciences
info:eu-repo/semantics/nonPublished

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Livros sobre o assunto "Thermonuclear plasmas"

1

Schilham. Stratified thermonuclear plasmas. Eindhoven: University of Eindhoven, 2002.

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2

Hugenholtz, Coenraad Albertus Jacobus. Microwave interferometer and reflectometer techniques for thermonuclear plasmas. [s.l.]: [s.n.], 1990.

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3

G, Basov N., ed. Heating and compression of thermonuclear targets by laser beam. Cambridge: Cambridge University Press, 1986.

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4

Peters, Michiel. Electron heat transport in current carrying and currentless thermonuclear plasmas: Tokamaks and stellarators compared. [s.l.]: [s.n.], 1996.

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5

Zohuri, Bahman. Plasma Physics and Controlled Thermonuclear Reactions Driven Fusion Energy. Cham: Springer International Publishing, 2016. http://dx.doi.org/10.1007/978-3-319-47310-9.

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6

E, Stott P., e International School of Plasma Physics "Piero Caldirola" Workshop on Diagnostics for Experimental Fusion Reactors (1997 : Varenna, Italy), eds. Diagnostics for experimental thermonuclear fusion reactors 2. New York: Plenum Press, 1998.

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7

1939-, Janev R. K., e Drawin Hans-Werner, eds. Atomic and plasma-material interaction processes in controlled thermonuclear fusion. Amsterdam: Elsevier, 1993.

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8

R, Krikorian, ed. Plasma physics and controlled thermonuclear fusion: Proceedings of the II Latin-American Workshop on plasma physics and controlled thermonuclear fusion, Medellín, Colombia, 16-28 Feb. 1987. Singapore: World Scientific, 1989.

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9

Russia) International Seminar on High Energy Physics and Thermonuclear Research (3rd 1998 Novosibirsk. 3 International Seminar on High Energy Physics and Thermonuclear Research: Novosibirsk, Russia, May 11-15, 1998 : proceedings. Editado por Baĭer, V. N. (Vladimir Nikolaevich) e Institut i︠a︡dernoĭ fiziki im. G.I. Budkera. Novosibirsk: Budker Institute of Nuclear Physics, 1998.

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10

Coppi, B. Physics of Plasmas Close to Thermonuclear Conditions: Proceedings of the Course Held in Varenna, Italy, 27 August - 8 September 1979. Elsevier Science & Technology Books, 2013.

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Capítulos de livros sobre o assunto "Thermonuclear plasmas"

1

Isler, R. C. "Spectroscopy of Divertor Plasmas". In Diagnostics for Experimental Thermonuclear Fusion Reactors, 541–48. Boston, MA: Springer US, 1996. http://dx.doi.org/10.1007/978-1-4613-0369-5_67.

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2

Zurro, B., A. Ibarra, A. U. Acuña, R. Sastre e K. J. McCarthy. "Development of Luminescent Detectors for Hot Plasmas". In Diagnostics for Experimental Thermonuclear Fusion Reactors, 311–14. Boston, MA: Springer US, 1996. http://dx.doi.org/10.1007/978-1-4613-0369-5_36.

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3

Sánchez, J., T. Estrada, E. de la Luna, V. Zhuravlev, M. Francés e B. Brañas. "Reflectometry Density Profile Measurements in Turbulent Plasmas". In Diagnostics for Experimental Thermonuclear Fusion Reactors 2, 151–54. Boston, MA: Springer US, 1998. http://dx.doi.org/10.1007/978-1-4615-5353-3_14.

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Johnson, L. C., C. W. Barnes, R. E. Bell, M. Bitter, R. V. Budny, C. E. Bush, D. S. Darrow et al. "Fusion Product Measurements in D-T Plasmas in TFTR". In Diagnostics for Experimental Thermonuclear Fusion Reactors, 369–78. Boston, MA: Springer US, 1996. http://dx.doi.org/10.1007/978-1-4613-0369-5_43.

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Zerbini, M., P. Buratti e P. Amadeo. "Experimental Results of Amplitude Modulation Reflectometry on High Density Tokamak Plasmas". In Diagnostics for Experimental Thermonuclear Fusion Reactors, 175–78. Boston, MA: Springer US, 1996. http://dx.doi.org/10.1007/978-1-4613-0369-5_19.

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Gorini, G., L. Ballabio, J. Källne, S. Conroy, J. Frenje, G. Ericsson, P. Prandoni, M. Tardocchi e E. Traneus. "Fuel Density Measurement in Burning Plasmas Using Neutron Spectrometry". In Diagnostics for Experimental Thermonuclear Fusion Reactors 2, 463–70. Boston, MA: Springer US, 1998. http://dx.doi.org/10.1007/978-1-4615-5353-3_56.

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Shaviv, Nir J., e Giora Shaviv. "The Electrostatic Screening of Thermonuclear Reactions in Astrophysical Plasmas". In White Dwarfs, 43–48. Dordrecht: Springer Netherlands, 1997. http://dx.doi.org/10.1007/978-94-011-5542-7_6.

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Mayer, M., R. Behrisch, C. Gowers, P. Andrew e A. T. Peacock. "Change of the Optical Reflectivity of Mirror Surfaces Exposed to Jet Plasmas". In Diagnostics for Experimental Thermonuclear Fusion Reactors 2, 279–86. Boston, MA: Springer US, 1998. http://dx.doi.org/10.1007/978-1-4615-5353-3_33.

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9

Razdobarin, G. T., e E. E. Mukhin. "Status of Thomson Scattering Diagnostic Design for ITER X-Point and Divertor Plasmas". In Diagnostics for Experimental Thermonuclear Fusion Reactors 2, 237–46. Boston, MA: Springer US, 1998. http://dx.doi.org/10.1007/978-1-4615-5353-3_26.

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Cecil, F. E., J. C. Barbour, P. v. Belle, D. Darrow, M. Hone, O. N. Jarvis, S. Kern et al. "Development of a Thin-Foil Faraday Collector Array as a Lost Alpha Particle Diagnostic for High Yield D-T Fusion Plasmas". In Diagnostics for Experimental Thermonuclear Fusion Reactors 2, 525–28. Boston, MA: Springer US, 1998. http://dx.doi.org/10.1007/978-1-4615-5353-3_64.

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Trabalhos de conferências sobre o assunto "Thermonuclear plasmas"

1

Defrance, P., J. Lecointre, J. J. Jureta, D. S. Belic, R. K. Janev, Ali Al-Hajry, Ahmad Umar et al. "Electron Impact Dissociation of Molecular Ions for Thermonuclear Plasmas". In PROCEEDINGS OF THE FIFTH SAUDI PHYSICAL SOCIETY CONFERENCE (SPS5). AIP, 2011. http://dx.doi.org/10.1063/1.3638079.

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2

Matsuura, H., e Y. Nakao. "Effect of Nuclear Elastic Scattering on Ion Heating in Thermonuclear Plasmas". In 21st IEEE/NPS Symposium on Fusion Engineering SOFE 05. IEEE, 2005. http://dx.doi.org/10.1109/fusion.2005.252979.

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3

Cesario, R., L. Amicucci, A. Cardinali, C. Castaldo, A. A. Tuccillo, Cynthia K. Phillips e James R. Wilson. "Lower hybrid current drive at plasma densities required for thermonuclear reactors". In RADIO FREQUENCY POWER IN PLASMAS: Proceedings of the 19th Topical Conference. AIP, 2011. http://dx.doi.org/10.1063/1.3665006.

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4

Miramar Blazquez, Jose F. "Study of channeling in thermonuclear plasmas by laser in the inertial confinement fusion". In 2008 IEEE 35th International Conference on Plasma Science (ICOPS). IEEE, 2008. http://dx.doi.org/10.1109/plasma.2008.4590693.

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5

Baldi, L., S. Digiovenale, T. Fortunato, G. Maffia, F. Mirizzi, M. Roccon, M. Sassi e A. A. Tuccillo. "A 8 GHz, high power, microwave system for the heating of thermonuclear plasmas". In 23rd European Microwave Conference, 1993. IEEE, 1993. http://dx.doi.org/10.1109/euma.1993.336580.

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6

Dreischuh, Tanja N., Ljuan L. Gurdev e Dimitar V. Stoyanov. "Efficiency of determining electron temperature and concentration in thermonuclear plasmas by Thomson scattering lidar". In Seventeenth International School on Quantum Electronics: Laser Physics and Applications, editado por Tanja N. Dreischuh e Albena T. Daskalova. SPIE, 2013. http://dx.doi.org/10.1117/12.2014282.

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Gurdev, Ljuan L., Tanja N. Dreischuh e Dimitar V. Stoyanov. "Potential accuracies of some new approaches for determination by Thomson scattering lidar of the electron temperature profiles in thermonuclear plasmas". In 15th International School on Quantum Electronics: Laser Physics and Applications, editado por Tanja Dreischuh, Elena Taskova, Ekaterina Borisova e Alexander Serafetinides. SPIE, 2008. http://dx.doi.org/10.1117/12.822512.

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8

Krikorian, R. "Plasma Physics and Controlled Thermonuclear Fusion". In II Latin American Workshop on Plasma Physics and Controlled Thermonuclear Fusion. WORLD SCIENTIFIC, 1989. http://dx.doi.org/10.1142/9789814541305.

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9

Nomoto, Ken’ichi, Koichi Iwamoto, Toshikazu Shigeyama e Hideaki Takabe. "Instabilities of nuclear flames in thermonuclear supernovae". In Laser interaction and related plasma phenomena: 12th international conference. AIP, 1996. http://dx.doi.org/10.1063/1.50469.

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10

Thumm, Manfred. "Progress on gyrotrons foriterand future thermonuclear fusion reactors". In 2010 IEEE 37th International Conference on Plasma Sciences (ICOPS). IEEE, 2010. http://dx.doi.org/10.1109/plasma.2010.5534112.

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Relatórios de organizações sobre o assunto "Thermonuclear plasmas"

1

Chaniotakis, E. Ignition and burn control characteristics of thermonuclear plasmas. Office of Scientific and Technical Information (OSTI), junho de 1990. http://dx.doi.org/10.2172/6692076.

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2

Coppi, B., S. Cowley, P. Detragiache, R. Kulsrud e F. Pegoraro. High energy components and collective modes in thermonuclear plasmas. Office of Scientific and Technical Information (OSTI), fevereiro de 1986. http://dx.doi.org/10.2172/6093225.

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3

N.N. Gorelenkov, H.L. Berk, R. Budny, C.Z. Cheng, G.-Y. Fu, W.W. Heidbrink, G. Kramer, D. Meade e and R. Nazikian. Study of Thermonuclear Alfven Instabilities in Next Step Burning Plasma Experiments. Office of Scientific and Technical Information (OSTI), julho de 2002. http://dx.doi.org/10.2172/807248.

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4

Cohen, S., R. Mattas e K. Werley. Plasma-materials interaction issues for the International Thermonuclear Experimental Reactor (ITER). Office of Scientific and Technical Information (OSTI), fevereiro de 1992. http://dx.doi.org/10.2172/5588594.

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Cohen, S. A., R. F. Mattas e K. A. Werley. Plasma-materials interaction issues for the International Thermonuclear Experimental Reactor (ITER). Office of Scientific and Technical Information (OSTI), fevereiro de 1992. http://dx.doi.org/10.2172/10124439.

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6

Hirooka, Y., R. W. Conn, R. Doerner, M. Khandagle, R. Causey, K. Wilson, D. Croessmann et al. Bulk-bronzied graphites for plasma-facing components in ITER (International Thermonuclear Experimental Reactor). Office of Scientific and Technical Information (OSTI), junho de 1990. http://dx.doi.org/10.2172/6428340.

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7

Castro, R. G., K. E. Elliott, K. J. Hollis, A. H. Bartlett e R. D. Watson. The development of beryllium plasma spray technology for the International Thermonuclear Experimental Reactor (ITER). Office of Scientific and Technical Information (OSTI), fevereiro de 1999. http://dx.doi.org/10.2172/314128.

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Burchell, T. (The international thermonuclear experimental reactor (ITER) workshop on plasma facing components and materials data base). Office of Scientific and Technical Information (OSTI), março de 1990. http://dx.doi.org/10.2172/7242771.

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Warshaw, S. I. The TDF System for Thermonuclear Plasma Reaction Rates, Mean Energies and Two-Body Final State Particle Spectra. Office of Scientific and Technical Information (OSTI), julho de 2001. http://dx.doi.org/10.2172/15006194.

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