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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 [http://univ.micinn.fecyt.es/ciencia/jsp/plantilla.jsp?area=instalaciones&id=21 Large Scientific Installations].
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>[http://www.ornl.gov/info/reports/1987/3445602635147.pdf T.C. Hender et al, ''Studies of a flexible heliac configuration'', Report ORNL/TM-10374 (1987) OSTI ID: 6007697]</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 1999.
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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[[File:TJ-II_3D_perspective.jpg|300px|thumb|right|TJ-II perspective view]]
[[File:TJ-II_3D_perspective.jpg|300px|thumb|right|TJ-II perspective view]]


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 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.  
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, ''&iota;/2&pi;'':          ||  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 at the LNF]].
Also refer to [[LNF:Plasma Physics]].


== Operation ==
== Operation ==


The electric energy required for a TJ-II discharge is obtained from a [[TJ-II:Power supply|flywheel generator]].
* 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 coils are cooled by means of a [[TJ-II:cooling system|cooling system]].
* 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.
 
* A [[TJ-II:Biasing probe|biasing probe]] can be used to apply a bias potential at the edge.
Two movable [[TJ-II:Limiter|limiters]] can be used to limit the plasma.
* A [[TJ-II:Paddle|mechanical paddle]] is used to suppress runaway electrons during current ramp-up and ramp-down.
 
A [[TJ-II:Biasing probe|biasing probe]] can be used to apply a bias potential at the edge.


== Heating and fuelling ==
== Heating and fuelling ==
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== Diagnostics ==
== Diagnostics ==


[[File:TJ-II_top_view_2009.jpg|400px|thumb|right|TJ-II in 2009; front left: Thomson Scattering; left and bottom right: NBI; top: HIBP]]
[[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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''Passive diagnostics''
''Passive diagnostics''
* [[TJ-II:Magnetics|Magnetics]]
* [[TJ-II:Magnetics|Magnetics]]
* [[TJ-II:Halpha monitors|H&alpha; monitors]]
* [[TJ-II:Halpha monitors|Halpha monitors]]
* [[TJ-II:Electron Cyclotron Emission|Electron Cyclotron Emission]]
* [[TJ-II:Electron Cyclotron Emission|Electron Cyclotron Emission]]
* [[TJ-II:Soft X-rays|Soft X-rays]]
* [[TJ-II:Soft X-rays|Soft X-rays]]
* [[TJ-II:Multifilter electron temperature diagnostic|Multifilter electron temperature diagnostic]]
* [[TJ-II:Bolometry|Bolometry]]
* [[TJ-II:Bolometry|Bolometry]]
* [[TJ-II:Spectroscopy|Spectroscopy]]
* [[TJ-II:Spectroscopy|Spectroscopy]]
* [[TJ-II:Charge exchange spectroscopy|Charge exchange 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: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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* [[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
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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
* [[Master]] - 1D Master Equation solver for [[Non-diffusive transport|non-diffusive transport]]
* [[TRUBA]]- Microwave beam/ray tracing including electron Bernstein wave calculations.


=== Data analysis ===
=== Data analysis ===
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* [[EBITA]] - Tomographic reconstruction
* [[EBITA]] - Tomographic reconstruction
* [[TJ-II:Tomography|Tomography]] - Tomographic reconstruction based on mode decomposition in flux surface geometry
* [[TJ-II:Tomography|Tomography]] - Tomographic reconstruction based on mode decomposition in flux surface geometry
* [[TJ-II:FM|FM]] - Density reconstruction for the reflectometer
 
=== Software tools ===
* [[MDSplus]]


== References ==
== References ==
<references />
<references />
[[Category:Toroidal confinement devices]]
Retrieved from "http://wiki.fusenet.eu/wiki/Special:MobileDiff/1604...7857"

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