TJ-II: Difference between revisions

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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://www.micinn.es/portal/site/MICINN/menuitem.6f2062042f6a5bc43b3f6810d14041a0/?vgnextoid=cb09846085f90210VgnVCM1000001034e20aRCRD 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 1997.
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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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 ==
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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: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.
* Two movable [[TJ-II:Limiter|limiters]] can be used to limit the plasma.
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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.
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