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TJ-II is a flexible Heliac installed at Spain's [[Laboratorio Nacional de Fusión|National Fusion Laboratory]]. It is currently operational. | [[File:TJII_model.jpg|500px|thumb|right|TJ-II Model]] | ||
TJ-II is a flexible Heliac installed at Spain's [[Laboratorio Nacional de Fusión|National Fusion Laboratory]]. | |||
It is one of Spain's [https://www.ciencia.gob.es/Organismos-y-Centros/Infraestructuras-Cientificas-y-Tecnicas-Singulares-ICTS.html Unique Scientific and Technical Infrastructures]. | |||
It is currently operational. | |||
== History == | == History == | ||
[[File:Foto_grupo_Fusion_1996.jpg|300px|thumb|left|TJ-II and the TJ-II Team in 1996]] | |||
The first plasma was produced in | The flexible Heliac TJ-II was designed on the basis of calculations performed by the team of physicists and engineers of [[CIEMAT]], in collaboration with the Oak Ridge National Laboratory ([http://en.wikipedia.org/wiki/ORNL ORNL], USA) and the Institut für PlasmaPhysik at Garching ([http://en.wikipedia.org/wiki/Max-Planck-Institut_f%C3%BCr_Plasmaphysik IPP], Germany). | ||
<ref>T.C. Hender et al, ''Studies of a flexible heliac configuration'', [https://www.osti.gov/biblio/6007697-studies-flexible-heliac-configuration Report ORNL/TM-10374 (1987) OSTI ID: 6007697]</ref> | |||
The TJ-II project received preferential support from [[Euratom]] for phase I (Physics) in 1986<ref>Application for EURATOM preferential support (Phase I) - TJ-II EXPERIMENT, [http://www-fusion.ciemat.es/InternalReport/fusion_1985.pdf Technical report, Asociación EURATOM/CIEMAT, 1985]</ref> and for phase II (Engineering) in 1990<ref>Application for EURATOM preferential support (Phase II) - TJ-II EXPERIMENT, [http://www-fusion.ciemat.es/InternalReport/fusion_1989b.pdf Technical report, Asociación EURATOM/CIEMAT, 1989]</ref>. The [[TJ-II:Construction|construction of this flexible Heliac]] was carried out in parts according to its constitutive elements, which were commissioned to various European companies, although 60% of the investments reverted back to Spanish companies. | |||
The first plasma was produced in 1997.<ref>[http://www.ciemat.es/vertices/vertices-292017/Vertices29/pdf/VERTICES29.pdf Special issue of CIEMAT's magazine ''Vertices''] commemorating 20 years of experiments (December, 2017)</ref> | |||
== Precedents == | == Precedents == | ||
TJ-II is the third magnetic confinement device in a series. In 1983, the device [[TJ-I]] was taken into operation. | TJ-II is the third magnetic confinement device in a series. In 1983, the device [[TJ-I]] was taken into operation. | ||
The denomination of this device is due to the abbreviation of "Tokamak de la | The denomination of this device is due to the abbreviation of "Tokamak de la Junta de Energía Nuclear", this being the former denomination of [[CIEMAT]]. The abbreviation was maintained for successive devices for administrative reasons. | ||
In 1994, the torsatron [[TJ-IU]] was taken into operation. This was the first magnetic confinement device entirely built in Spain. Currently, [[TJ-IU]] is located at the [http://www.ipf.uni-stuttgart.de/index_e.html University of Stuttgart] in Germany under the name of [[TJ-K]]. | In 1994, the torsatron [[TJ-IU]] was taken into operation. This was the first magnetic confinement device entirely built in Spain. Currently, [[TJ-IU]] is located at the [http://www.ipf.uni-stuttgart.de/index_e.html University of Stuttgart] in Germany under the name of [[TJ-K]] (the 'K' stands for Kiel, its first location in Germany, before arriving in Stuttgart). | ||
== Description == | == Description == | ||
In TJ-II, the magnetic trap is obtained by means of various sets of coils that completely determine the magnetic surfaces before plasma initiation. The toroidal field is created by 32 coils. The | [[File:TJ-II_3D_perspective.jpg|300px|thumb|right|TJ-II perspective view]] | ||
In TJ-II, the magnetic trap is obtained by means of [[TJ-II:Coil system|various sets of coils]] that completely determine the magnetic surfaces before plasma initiation. The toroidal field is created by 32 coils. The three-dimensional twist of the central axis of the configuration is generated by means of two central coils: one circular and one helical. The horizontal position of the plasma is controlled by the vertical field coils. The combined action of these magnetic fields generate bean-shaped magnetic surfaces that guide the particles of the plasma so that they do not collide with the [[TJ-II:Vacuum system|vacuum vessel]] wall. | |||
TJ-II discharges last around 0.25 s, with a repetition frequency of about 7 minutes. | TJ-II discharges last around 0.25 s, with a repetition frequency of about 7 minutes. | ||
== | {| class="wikitable" align="center" border="1" | ||
!''Parameter'' !!''Value''!!''Unit'' | |||
|- | |||
|Major radius, ''R<sub>0</sub>'': || 1.5 || m | |||
|- | |||
|Minor radius, ''a'': || < 0.22 || m | |||
|- | |||
|Plasma volume, ''V'': || 1 || m<sup>3</sup> | |||
|- | |||
|Field periods: || 4 || | |||
|- | |||
|[[TJ-II:Coil system|TF coils]]: || 32 || | |||
|- | |||
|Number of ports: || 104 || | |||
|- | |||
|Rotational transform, ''ι/2π'': || 0.9 - 2.5 || | |||
|- | |||
|Magnetic field on axis, ''B<sub>0</sub>'': || ~1 || T | |||
|- | |||
|ECRH heating power, ''P<sub>ECRH</sub>'': || < 600 || kW | |||
|- | |||
|NBI heating power, ''P<sub>NBI</sub>'': || < 2 || MW | |||
|- | |||
|Pulse length: || < 200 || ms | |||
|} | |||
== Goals and Research == | |||
[[ | The objective of the experimental program of TJ-II is to investigate the physics of a device with a helical magnetic axis having a great flexibility in its magnetic configuration, and to contribute to the international effort regarding the study of magnetic confinement devices for fusion. | ||
Also refer to [[LNF:Plasma Physics]]. | |||
== Operation == | == Operation == | ||
The electric energy required for a TJ-II discharge is obtained from a [[TJ-II: | * A [[TJ-II:Vacuum system|vacuum system]] controls the pressure inside the vacuum vessel. | ||
The coils are cooled by means of a [[TJ-II: | * The electric energy required for a TJ-II discharge is obtained from a [[TJ-II:Power supply|flywheel generator]]. | ||
* The [[TJ-II:Coil system|coils]] are cooled by means of a [[TJ-II:Cooling system|cooling system]]. | |||
* An extensive set of systems is available to perform [[TJ-II:Plasma Wall Interaction|plasma wall conditioning]]. | |||
* Two movable [[TJ-II:Limiter|limiters]] can be used to limit the plasma. | |||
* A [[TJ-II:Biasing probe|biasing probe]] can be used to apply a bias potential at the edge. | |||
* A [[TJ-II:Paddle|mechanical paddle]] is used to suppress runaway electrons during current ramp-up and ramp-down. | |||
== Heating and fuelling == | == Heating and fuelling == | ||
In order to heat | In order to fuel and heat the TJ-II plasma, the following systems are used: | ||
* [[TJ-II:Gas puff|Gas puff]] | * [[TJ-II:Gas puff|Gas puff]] | ||
* [[TJ-II:Pellet injector|Pellet injector]] | * [[TJ-II:Electron Cyclotron Resonant Heating|Electron Cyclotron Resonant Heating]] (ECRH) | ||
* [[TJ-II:Neutral Beam Injection|Neutral Beam Injection]] (NBI) | |||
* [[TJ-II:Electron Bernstein Wave Heating|Electron Bernstein Wave Heating]] (EBWH) | |||
* [[TJ-II:Pellet injector|Pellet injector]] (PI) | |||
== Control and data acquisition == | == Control and data acquisition == | ||
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== Diagnostics == | == Diagnostics == | ||
TJ-II is fitted with an extensive set of diagnostic systems. For information on | [[File:TJ-II_top_view.jpg|400px|thumb|right|TJ-II in 2012; front left: [[TJ-II:Thomson Scattering|Thomson Scattering]]; left and bottom right: [[TJ-II:Neutral Beam Injection|NBI]]; top: the inclined structures are two [[TJ-II:Heavy Ion Beam Probe|HIBP]] systems. Also visible on top, up front, is the reciprocating [[TJ-II:Langmuir Probes|Langmuir Probe]].]] | ||
[[TJ-II: | |||
* [[TJ-II:Halpha | TJ-II is fitted with an extensive set of diagnostic systems installed in its 96 access [[TJ-II:Ports|ports]]. For information on the magnetic coordinate system (required for cross-diagnostic comparisons), see [[TJ-II:Magnetic_coordinates|TJ-II magnetic coordinates]]. | ||
* [[TJ-II: | |||
''Passive diagnostics'' | |||
* [[TJ-II:Magnetics|Magnetics]] | |||
* [[TJ-II:Halpha monitors|Halpha monitors]] | |||
* [[TJ-II:Electron Cyclotron Emission|Electron Cyclotron Emission]] | |||
* [[TJ-II:Soft X-rays|Soft X-rays]] | |||
* [[TJ-II:Multifilter electron temperature diagnostic|Multifilter electron temperature diagnostic]] | |||
* [[TJ-II:Bolometry|Bolometry]] | |||
* [[TJ-II:Spectroscopy|Spectroscopy]] | |||
* [[TJ-II:Charge exchange spectroscopy|Charge exchange spectroscopy]] | |||
* [[TJ-II:Compact Neutral Particle Analyzer|Compact Neutral Particle Analyzer]] | |||
* [[TJ-II:Fast ion loss probe|Fast ion loss probe]] | |||
* [[TJ-II:Retarding Field Analyzer|Retarding Field Analyzer]] | |||
* [[TJ-II:Fast camera|Fast camera]] | |||
''Active diagnostics'' | |||
* [[TJ-II:Interferometry|Interferometry]] | * [[TJ-II:Interferometry|Interferometry]] | ||
* [[TJ-II:Reflectometry|Reflectometry]] | * [[TJ-II:Reflectometry|Reflectometry]] | ||
* [[TJ-II:Heavy Ion Beam Probe|Heavy Ion Beam Probe]] | * [[TJ-II:Heavy Ion Beam Probe|Heavy Ion Beam Probe]] | ||
* [[TJ-II:Langmuir Probes|Langmuir Probes]] | * [[TJ-II:Langmuir Probes|Langmuir Probes]] | ||
* [[TJ-II:Thomson Scattering|Thomson Scattering]] | * [[TJ-II:Thomson Scattering|Thomson Scattering]] | ||
* [[TJ-II:Diagnostic neutral beam|Diagnostic neutral beam]] | |||
* [[TJ-II:Helium Beam|Helium Beam]] | * [[TJ-II:Helium Beam|Helium Beam]] | ||
* [[TJ-II: | * [[TJ-II:Lithium Beam|Lithium Beam]] | ||
[http://www-fusion.ciemat.es/cgi-bin/TJII_data.cgi Interactive on-line data visualization] | |||
== Numerical resources == | == Numerical resources == | ||
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* [[VMEC]] - 3D Plasma equilibrium, assuming nested flux surfaces | * [[VMEC]] - 3D Plasma equilibrium, assuming nested flux surfaces | ||
* [[PIES]] - 3D Plasma equilibrium | * [[PIES]] - 3D Plasma equilibrium | ||
* [[HL]] - Field line following code | |||
* [[ASTRA]] - Plasma transport | * [[ASTRA]] - Plasma transport | ||
* [[PROCTR]] - Plasma transport | * [[PROCTR]] - Plasma transport | ||
* [[EIRENE]] | * [[EUTERPE]] - Gyrokinetic code | ||
* [[EIRENE]] - A Monte Carlo neutral gas transport code | |||
* [[FAFNER]] | * [[FAFNER]] | ||
* [[CUTIE]] - Full-tokamak fluid turbulence | * [[CUTIE]] - Full-tokamak fluid turbulence | ||
* [[MOCA]] - Monte Carlo Neoclassical transport code | * [[MOCA]] - Monte Carlo [[Neoclassical transport]] code | ||
* [[ | * [[DKES]] - [[Neoclassical transport]] code | ||
* [[TRECE]] - Microwave ray tracing | |||
* [[TRUBA]]- Microwave beam/ray tracing including electron Bernstein wave calculations. | |||
=== Data analysis === | === Data analysis === | ||
* [[Wave_ana]] - Linear and non-linear data analysis, spectral analysis using Fourier and Wavelets | * [[Wave_ana]] - Linear and non-linear data analysis, spectral analysis using Fourier and Wavelets | ||
* [[EBITA]] - Tomographic reconstruction | * [[EBITA]] - Tomographic reconstruction | ||
* [[ | * [[TJ-II:Tomography|Tomography]] - Tomographic reconstruction based on mode decomposition in flux surface geometry | ||
* [[ | |||
=== Software tools === | |||
* [[MDSplus]] | |||
== | == References == | ||
<references /> | |||
[[Category:Toroidal confinement devices]] | |||