Spherical tokamak development in Brazil

Ludwig, G. O.; Bosco, E. Del; Ferreira, Jonathan; Berni, L. A.; Oliveira, R. M.; Andrade, M.C.R.; Shibata, C.S.; Ueda, M.; Barbosa, L.F.W.; Barroso, Joaquim J.; Castro, P.J.; Patire, H.

doi:10.1590/s0103-97332003000400041

Cited by 13 publications

(11 citation statements)

References 19 publications

(17 reference statements)

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“…El Tokamak esférico MEDUSA-CR permite calentamiento ECR lazando las microondas desde el lado de alto campo, en inglés High Field Side (HFS) y desde el lado de bajo campo, en inglés Low Field Side (LFS). Por lo anterior se seleccionó un girotrón de rango medio, a una frecuencia de 30 GHz y una potencia entre 50 kW y 100 kW, similar al empleado en ETE [7]. La idea es solicitar ayuda técnica y precios especiales para el Laboratorio de Plasmas del TEC, dado que un girotrón, con las especificaciones apuntadas, de 30 GHz y 100 kW, tiene un costo de más de $20 000 (USD).…”

Section: Resultsunclassified

Simulación de plasma y diseño de sistemas para operación y diagnóstico en el Tokamak esférico MEDUSA-CR

Araya-Solano

Ramirez-Jimenez²,

Solano-Piedra³

et al. 2022

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Este proyecto simuló escenarios de confinamiento que buscan analizar diferentes formas de la sección transversal del plasma y de esta manera prever el parámetro beta óptimo en un tokamak esférico de baja razón de aspecto como lo es MEDUSA-CR. Además, se busca diseñar sistemas para operación y diagnóstico en este dispositivo. Finalmente, en este proyecto proponemos un experimento único como prueba de principio utilizando antenas RF para inducir ondas de Alfvén en un Tokamak esférico. Las simulaciones de las interacciones del plasma con las ondas electromagnéticas RF y ECRH permiten explorar en este dispositivo escenarios de calentamiento optimizado que también son del interés de la comunidad científica debido a que la alta temperatura es un requisito indispensable para procesos de fusión.

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Section: Resultsunclassified

Simulación de plasma y diseño de sistemas para operación y diagnóstico en el Tokamak esférico MEDUSA-CR

Araya-Solano

Ramirez-Jimenez²,

Solano-Piedra³

et al. 2022

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“…A systematic measurement and study of plasma edge parameters will be carried out in the ETE spherical tokamak [7]. The project includes the implementation and upgrading of the diagnostics (Thomson scattering, neutral lithium beam probe, electrostatic probes, spectroscopic and magnetic measurements and ultra-soft x-ray photodiode arrays, among others) that will be used to study the plasma boundary properties.…”

Section: Direct Contribution Of Small Tokamaks To Mainstream Fusion R...mentioning

confidence: 99%

Joint research using small tokamaks

Gryaznevich¹,

Bosco²,

Malaquias³

et al. 2005

Nucl. Fusion

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Small tokamaks have an important role in fusion research. More than 40 small tokamaks are operational. Research on small tokamaks has created a scientific basis for the scaling-up to larger tokamaks. Well-known scientific and engineering schools, which are now determining the main directions of fusion science and technology, have been established through research on small tokamaks. Combined efforts within a network of small and medium size tokamaks will further enhance the contribution of small tokamaks. A new concept of interactive coordinated research using small tokamaks in the mainstream fusion science areas, in testing of new diagnostics, materials and technologies as well as in education, training and broadening of the geography of fusion research in the scope of the IAEA Coordinated Research Project, is presented.

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“…The ETE (Experimento Tokamak Esférico) is a medium-size spherical torus with an aspect ratio of 1.5, major radius of 0.3 m, toroidal field of 0.4 T and plasma current of 0.22 MA for the first stage of operation [1]. The objectives of the project are focused on plasma edge investigation, development of diagnostics and training on tokamak operation.…”

Section: The Ete Spherical Tokamakmentioning

confidence: 99%

Thomson scattering diagnostic on the ETE tokamak: status and progress

Berni¹,

Bosco²,

Oliveira³

et al. 2004

Braz. J. Phys.

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In order to measure the plasma temperature and density in the spherical tokamak ETE, a one-channel Thomson scattering system was implemented. During the upgrade of capacitor banks and optimization since the beginning of operation, the plasma pulse duration has increased from 1.5 ms up to 12 ms with plasma currents varying from 10 kA to 60 kA. During this phase, the electron temperature was increased from 20 eV to 160 eV with densities as high as 3.5×1019 m −3 . Presently, the Thomson scattering diagnostic is being upgraded based on the time-delay technique, that consists in using fibers of different lengths to transmit the scattered light signals to the same polychromator. This system will allow measurements of electron temperature and density profiles with ten spatial points per laser shot and per polychromator. This work describes in details the Thomson scattering system, presents a selection of results obtained by this system since the initial phase of operation, and shows details of the proposed upgrade of the Thomson scattering system. The ETE Spherical TokamakThe ETE (Experimento Tokamak Esférico) is a medium-size spherical torus with an aspect ratio of 1.5, major radius of 0.3 m, toroidal field of 0.4 T and plasma current of 0.22 MA for the first stage of operation [1]. The objectives of the project are focused on plasma edge investigation, development of diagnostics and training on tokamak operation. The vacuum vessel was manufactured with Inconel 625 with an external diameter and height of 1.2 m and an internal tube with a diameter of 0.18 m, which houses the ohmic solenoid and the inner legs of the toroidal coils. Good access for diagnostics is provided by 58 Conflat ports (12xCF14", 4xCF250 and 42xCF40). The vacuum system comprises three pumps: one turbo drag pump (1500 l/s) backed by an oilfree diaphragm (4 m 3 /h) and an auxiliary mechanical pump (30 m 3 /h). A base pressure of 7.8×10 −8 Torr was achieved after conditioning the vessel walls with baking (T < 150 o C) and DC glow discharge cleaning (GDC) with helium gas.There are three capacitor banks that storage energy for the toroidal, ohmic heating and equilibrium coils. The energy of the capacitor banks is being increased by adding more capacitors and increasing the maximum voltage rating. Presently, the acquisition system is based on CAMAC and oscilloscopes that, in a near future, will be replaced by VME technology [2]. Table 1 summarizes the status of the proposed diagnostics for ETE. For this initial phase a set of electromagnetic and optical diagnostics are already installed. For edge plasma investigation a 10 keV Fast Neutral Lithium Beam (FNLB) is under development with glassy β-eucryptite source that will furnish beam currents up to 1 mA/cm 2 [3]. To measure the electron temperature and density profiles a one-channel Thomson scattering (TS) system was implemented. Thomson Scattering Diagnostic in ETEThe TS is based on a 10 J Q-switched ruby laser (λ = 694.3 nm, pulse duration: 30 ns) that probes the plasma horizontally at the mid-plane. Th...

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Spherical tokamak development in Brazil

Cited by 13 publications

References 19 publications

Simulación de plasma y diseño de sistemas para operación y diagnóstico en el Tokamak esférico MEDUSA-CR

Simulación de plasma y diseño de sistemas para operación y diagnóstico en el Tokamak esférico MEDUSA-CR

Joint research using small tokamaks

Thomson scattering diagnostic on the ETE tokamak: status and progress

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