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TJ-II is a flexible Heliac installed at Spain's [[Laboratorio Nacional de Fusión|National Fusion Laboratory]]. | TJ-II is a flexible Heliac installed at Spain's [[Laboratorio Nacional de Fusión|National Fusion Laboratory]]. | ||
It is one of Spain's [ | 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. | It is currently operational. | ||
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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). | 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> | <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 and for phase II (Engineering) in 1990. 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. | <ref>A. Perea et al., "Physics Issues in the Design of TJ-II, Proc. 12th European Conf. Controlled Fusion and Plasma Physics, Budapest, Hungary, 1985, [http://libero.ipp.mpg.de/libero/PDF/EPS_12_Vol1_1985.pdf ECA Vol. 9F, Part I, p. 433], European Physical Society (1985)</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, [https://info.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, [https://info.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 | 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 == | ||
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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. | 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 == | ||
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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 == | == Goals and Research == | ||
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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. | 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 [[Plasma Physics | Also refer to [[LNF:Plasma Physics]]. | ||
== Operation == | == Operation == | ||
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* A [[TJ-II:Vacuum system|vacuum system]] controls the pressure inside the vacuum vessel. | * A [[TJ-II:Vacuum system|vacuum system]] controls the pressure inside the vacuum vessel. | ||
* The electric energy required for a TJ-II discharge is obtained from a [[TJ-II:Power supply|flywheel generator]]. | * 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: | * 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]]. | * 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. | * Two movable [[TJ-II:Limiter|limiters]] can be used to limit the plasma. | ||
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== Diagnostics == | == Diagnostics == | ||
[[File:TJ- | [[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 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 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]]. | ||
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* [[TJ-II:Compact Neutral Particle Analyzer|Compact Neutral Particle Analyzer]] | * [[TJ-II:Compact Neutral Particle Analyzer|Compact Neutral Particle Analyzer]] | ||
* [[TJ-II:Fast ion loss probe|Fast ion loss probe]] | * [[TJ-II:Fast ion loss probe|Fast ion loss probe]] | ||
* [[TJ-II:Retarding Field Analyzer|Retarding Field Analyzer]] | |||
* [[TJ-II:Fast camera|Fast camera]] | * [[TJ-II:Fast camera|Fast camera]] | ||
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* [[TJ-II:Helium Beam|Helium Beam]] | * [[TJ-II:Helium Beam|Helium Beam]] | ||
* [[TJ-II:Lithium Beam|Lithium Beam]] | * [[TJ-II:Lithium Beam|Lithium Beam]] | ||
[https://info.fusion.ciemat.es/cgi-bin/TJII_data.cgi Interactive on-line data visualization] | |||
== Numerical resources == | == Numerical resources == | ||
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* [[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 | |||
* [[KNOSOS]] - [[Neoclassical transport]] code | |||
* [[TRECE]] - Microwave ray tracing | * [[TRECE]] - Microwave ray tracing | ||
* [[TRUBA]]- Microwave beam/ray tracing including electron Bernstein wave calculations. | * [[TRUBA]]- Microwave beam/ray tracing including electron Bernstein wave calculations. |