https://isttok.tecnico.ulisboa.pt/~isttok.daemon/api.php?action=feedcontributions&feedformat=atom&user=Isttok-adminISTTOK - Contribuições do utilizador [pt]2026-07-29T02:47:21ZContribuições do utilizadorMediaWiki 1.30.0https://isttok.tecnico.ulisboa.pt/~isttok.daemon/index.php?title=ISTTOK_-_Wiki&diff=54ISTTOK - Wiki2018-04-21T16:14:55Z<p>Isttok-admin: /* =Innovative features */</p>
<hr />
<div><strong>IST Tokamak - ISTTOK</strong><br />
<br />
=Description=<br />
<br />
The ISTTOK Tokamak ("Instituto Superior Técnico TOKamak") is a research fusion reactor located at Instituto Superior Técnico.<br />
<br />
It has a circular cross-section due to a poloidal graphite limiter and an iron core transformer. This magnetic confinement experiment has been built from some components (supporting structure, vacuum chamber, copper shell, transformer, toroidal magnetic field coils, radio-frequency generator, and capacitor banks) of the precessor TORTUR tokamak which was de-commissioned by the Association EURATOM/FOM in 1988.<br />
<br />
[[File:Isttok.jpg]]<br />
==Goals and research objectives==<br />
The scientific programme has been based on: <br />
* Edge plasma turbulence studies;<br />
* Operation and control on alternating plasma current regimes; <br />
* Testing of liquid metal limiter concept; <br />
* Development and upgrade of diagnostics; <br />
* Test bed facility for new data acquisition concepts and hardware.<br />
===Theory contribution===<br />
Understanding turbulent transport is important to optimize the plasma confinement and for predicting the performance of future devices. Research on the comprehensive investigation of the multi-scale physics aspects of the edge turbulence, from its origin to the impact on transport including plasma-wall interaction. ISTTOK is ideal for edge physics studies due to its flexibility, low operation costs, short time scale for diagnostics implementation and compatibility with electrostatic probes. The universality of several edge physics phenomena was verified in different devices, confirming the relevance of these studies in small devices. Present activities include: <br />
*Contribute to a better understanding of spontaneously generated large-scale sheared flows and its role in regulating plasma transport.<br />
*Characterize and control the SOL intermittent transport.<br />
*Develop different electrical probes systems for edge studies.<br />
*Provide synergies between theory and experimental groups working on edge/SOL physics.<br />
*Develop analysis tools required to process the massive experimental data obtained . <br />
<br />
===Diagnostics development===<br />
<br />
Further studies on the ISTTOK plasma emissivity reconstruction using analytical methods, aiming at the best choice for real-time implementation in ISTTOK.<br />
Upgrade existing tomographic cameras to 3 x 16 channels in order to improve spatial resolution for enhanced emissivity reconstruction.<br />
Developing and building a retarding electrostatic field cylindrical energy analyzer (CEA) to measure plasma potentials in the core and their fluctuations. <br />
<br />
===Main achievements===<br />
<br />
====AC operation====<br />
Due to iron core saturation, operation of ISTTOK in single pulse mode is limited to 35 ms plasma duration. ISTTOK has suffer a major update of its control systems and power supplies to operate in AC mode increasing that parameter to more than 1000 ms. Within this line of research present activities include:<br />
*Operation of the tokamak ISTTOK in a multi-cycle alternating plasma current regime, to obtain long duration discharges.<br />
*Implementation of a real-time plasma control system and study of the control of long duration AC discharges in ISTTOK.<br />
*Development of advanced gas feed control to improve reproducible and reliable plasmas with high performance.<br />
Testing of liquid metal PFC<br />
<br />
====Liquid metals as PFCs====<br />
One of the most challenging issues with regards to the operation of a future fusion reactor is related to plasma-wall interaction. Solid materials exposed to fusion plasmas are known to suffer significant damage that reduces wall lifetime. Liquid metals have proven to be of relevance for PFC protection. Due to ISTTOK characteristics its programme has also focused on testing liquid metals PFC´s and their properties:<br />
*Develop a novel Liquid Metal Limiter based on micro-channels structures.<br />
*Build and test the new LML concept using gallium as liquid metal.<br />
*Expose this PFC to ISTTOK plasmas.<br />
*Study the behavior of the limiter surface temperature increase with liquid metal re-circulation.<br />
<br />
===Data acquisition and control===<br />
Implementation of a control system based on an optimized state-space model for real time control of the plasma current magnitude and centroid position retrieved by a twelve mirnov coils poloidal set.<br />
<br />
==Physical parameters==<br />
==Nominal plasma parameters==<br />
==Precedents==<br />
===TORTUR===<br />
Tortur was a tokamak designed in Grenoble with an initial primary to secondary winding ratio of 1:1. It starts to operate in 1974 at the FOM institute at Nieuwegein on the Neederlands.<br />
<br />
For the primary was used the stabilizing cooper-shell structure. A very high current had to be feed in this primary and short discharges were obtained (up to 8 ms). The vessel was a glass-quartz type.<br />
It's name origin was due to the acronym TORus for TURbulent heating. The underlying idea was to generate a suficient large current through the plasma to the limit were micro-instabilites will be excited enhancing the plasma resistivity and allowing further ohmic-heating.<br />
<br />
===TORTUR II===<br />
Tortur was not capable to diagnose properly the heated plasma and the high primary voltage needed posed severe insulation problems. In 1978 it undergoes a major upgrade. A new stainless steel 625 vessel was installed being divided in two C-sections and equiped with 33 ports of 35mm, constructed by Avica Equipment, England. Basically the vessel were made based on port structures welded together by a thin inconnel bellow of 0.15mm with an inner diameter of 200mm. Such thin metal structure allowed for a suficient fast penetration of the electric fiels used for the turbulent heating.<br />
<br />
===TORTUR III===<br />
By 1981 Tortur undergo again a vessel upgrade of the former one by the same manufacturer, assuming the actual design as in ISTTOK . A higher toroidal magnetic field was comissioned to improve confinement (up to 5T) in paralell with a structural reinforcement. Besides that it was equipped with a iron-core transformer yoke switchable in a 20:1 or 40:1 ratio, allowing to extend plasma discharges up to 50 ms. This pulse extension was possible as well by the instalation of a quadrupole for creating the necessary vertical and horizontal magnetic fields for plasma stability, centering the plasma in the chamber.<br />
<br />
By then the copper-shell was used sollely for the fast turbulent heating by firing a 25uF and up to 20kV for a steep-rising heating pulse at any presetable time duplicating the current(30->60kA) for ~10us. This thecnic allowed up to 1keV plasmas.<br />
<br />
Prior to the main discharges Tortur was "cleaned" by creating a glow discharge with the RF generator, heating the vessel up to 180ºC and producing small discharges with a low toroidal field (~50 mT) to outgas the vessel from impurities.<br />
<br />
It is worth to mentioned that all aquisition systems was based on CAMAC boards (5 crates) controlled by a PDP 11/23 Digital Inc. mainframe computer (-1988) and all data from the transient recorders being backuped on tape.<br />
<br />
===ISTTOK@XX===<br />
After the commissioning in Portugal, Tortur became the IST TOKamak, ISTTOK. During XX century is was operated with two capacitors banks as it's predecessor and only with forward current. The main systems have been updated, namely the vacuum systems, power supplies, the plant control systems and data acquisition.<br />
Discharges were started based on a cold plasma generated by the TORTUR RF generator (1.7MHz) but due to the high noise have been soon replaced by an electron beam source (80 eV, tungsten filament) situated on the high field side close to the SOL. The hot plasma was started by the high voltage bank (1-5kV, 1mF, 2-3ms) and then an electrolytic bank (0.4F, 350V, 40-50ms) took over.<br />
<br />
<br />
==Main components==<br />
===Innovative features===<br />
ISTTOK were since the beginning equiped with a tunnable toroidal field in view of ajusting the cyclotronic frequency to a desired value. This was quite uncommon in such class of tokamaks were the toroidal field was basically imposed either by a fixed transformer ratio from the grid or by using a capacitor bank. Conversily, due to the lack off avaiable power in campus, toroidal field had to be limited to ~0.5T.<br />
<br />
After a first exploitation phase with very similar Tortur parameters except for the toroidal field, ISTTOK@XXI became the first tokamak eqquiped with a switched IGBT primary circuit with a considerable larger capacitor bank (3.8F), allowing multiple AC discharges.<br />
<br />
ISTTOK is one of the few fusion devices eqquiped with an heavy ion beam diagnostic.<br />
<br />
===Toroidal field===<br />
====Geometry====<br />
====Current supply====<br />
<br />
===Poloidal fields===<br />
====Geometry====<br />
====Power amplifiers====<br />
<br />
===Vessel===<br />
<br />
===Vacuum system===<br />
<br />
===Gas injection===<br />
<br />
====Background pressure====<br />
<br />
====Gas puffing====<br />
<br />
====Residual gas analyser====<br />
<br />
====Broadband spectrometer====<br />
<br />
==References==<br />
<br />
==Links==<br />
[[Training]]</div>Isttok-adminhttps://isttok.tecnico.ulisboa.pt/~isttok.daemon/index.php?title=ISTTOK_-_Wiki&diff=52ISTTOK - Wiki2018-04-21T16:14:32Z<p>Isttok-admin: /* Main components */</p>
<hr />
<div><strong>IST Tokamak - ISTTOK</strong><br />
<br />
=Description=<br />
<br />
The ISTTOK Tokamak ("Instituto Superior Técnico TOKamak") is a research fusion reactor located at Instituto Superior Técnico.<br />
<br />
It has a circular cross-section due to a poloidal graphite limiter and an iron core transformer. This magnetic confinement experiment has been built from some components (supporting structure, vacuum chamber, copper shell, transformer, toroidal magnetic field coils, radio-frequency generator, and capacitor banks) of the precessor TORTUR tokamak which was de-commissioned by the Association EURATOM/FOM in 1988.<br />
<br />
[[File:Isttok.jpg]]<br />
==Goals and research objectives==<br />
The scientific programme has been based on: <br />
* Edge plasma turbulence studies;<br />
* Operation and control on alternating plasma current regimes; <br />
* Testing of liquid metal limiter concept; <br />
* Development and upgrade of diagnostics; <br />
* Test bed facility for new data acquisition concepts and hardware.<br />
===Theory contribution===<br />
Understanding turbulent transport is important to optimize the plasma confinement and for predicting the performance of future devices. Research on the comprehensive investigation of the multi-scale physics aspects of the edge turbulence, from its origin to the impact on transport including plasma-wall interaction. ISTTOK is ideal for edge physics studies due to its flexibility, low operation costs, short time scale for diagnostics implementation and compatibility with electrostatic probes. The universality of several edge physics phenomena was verified in different devices, confirming the relevance of these studies in small devices. Present activities include: <br />
*Contribute to a better understanding of spontaneously generated large-scale sheared flows and its role in regulating plasma transport.<br />
*Characterize and control the SOL intermittent transport.<br />
*Develop different electrical probes systems for edge studies.<br />
*Provide synergies between theory and experimental groups working on edge/SOL physics.<br />
*Develop analysis tools required to process the massive experimental data obtained . <br />
<br />
===Diagnostics development===<br />
<br />
Further studies on the ISTTOK plasma emissivity reconstruction using analytical methods, aiming at the best choice for real-time implementation in ISTTOK.<br />
Upgrade existing tomographic cameras to 3 x 16 channels in order to improve spatial resolution for enhanced emissivity reconstruction.<br />
Developing and building a retarding electrostatic field cylindrical energy analyzer (CEA) to measure plasma potentials in the core and their fluctuations. <br />
<br />
===Main achievements===<br />
<br />
====AC operation====<br />
Due to iron core saturation, operation of ISTTOK in single pulse mode is limited to 35 ms plasma duration. ISTTOK has suffer a major update of its control systems and power supplies to operate in AC mode increasing that parameter to more than 1000 ms. Within this line of research present activities include:<br />
*Operation of the tokamak ISTTOK in a multi-cycle alternating plasma current regime, to obtain long duration discharges.<br />
*Implementation of a real-time plasma control system and study of the control of long duration AC discharges in ISTTOK.<br />
*Development of advanced gas feed control to improve reproducible and reliable plasmas with high performance.<br />
Testing of liquid metal PFC<br />
<br />
====Liquid metals as PFCs====<br />
One of the most challenging issues with regards to the operation of a future fusion reactor is related to plasma-wall interaction. Solid materials exposed to fusion plasmas are known to suffer significant damage that reduces wall lifetime. Liquid metals have proven to be of relevance for PFC protection. Due to ISTTOK characteristics its programme has also focused on testing liquid metals PFC´s and their properties:<br />
*Develop a novel Liquid Metal Limiter based on micro-channels structures.<br />
*Build and test the new LML concept using gallium as liquid metal.<br />
*Expose this PFC to ISTTOK plasmas.<br />
*Study the behavior of the limiter surface temperature increase with liquid metal re-circulation.<br />
<br />
===Data acquisition and control===<br />
Implementation of a control system based on an optimized state-space model for real time control of the plasma current magnitude and centroid position retrieved by a twelve mirnov coils poloidal set.<br />
<br />
==Physical parameters==<br />
==Nominal plasma parameters==<br />
==Precedents==<br />
===TORTUR===<br />
Tortur was a tokamak designed in Grenoble with an initial primary to secondary winding ratio of 1:1. It starts to operate in 1974 at the FOM institute at Nieuwegein on the Neederlands.<br />
<br />
For the primary was used the stabilizing cooper-shell structure. A very high current had to be feed in this primary and short discharges were obtained (up to 8 ms). The vessel was a glass-quartz type.<br />
It's name origin was due to the acronym TORus for TURbulent heating. The underlying idea was to generate a suficient large current through the plasma to the limit were micro-instabilites will be excited enhancing the plasma resistivity and allowing further ohmic-heating.<br />
<br />
===TORTUR II===<br />
Tortur was not capable to diagnose properly the heated plasma and the high primary voltage needed posed severe insulation problems. In 1978 it undergoes a major upgrade. A new stainless steel 625 vessel was installed being divided in two C-sections and equiped with 33 ports of 35mm, constructed by Avica Equipment, England. Basically the vessel were made based on port structures welded together by a thin inconnel bellow of 0.15mm with an inner diameter of 200mm. Such thin metal structure allowed for a suficient fast penetration of the electric fiels used for the turbulent heating.<br />
<br />
===TORTUR III===<br />
By 1981 Tortur undergo again a vessel upgrade of the former one by the same manufacturer, assuming the actual design as in ISTTOK . A higher toroidal magnetic field was comissioned to improve confinement (up to 5T) in paralell with a structural reinforcement. Besides that it was equipped with a iron-core transformer yoke switchable in a 20:1 or 40:1 ratio, allowing to extend plasma discharges up to 50 ms. This pulse extension was possible as well by the instalation of a quadrupole for creating the necessary vertical and horizontal magnetic fields for plasma stability, centering the plasma in the chamber.<br />
<br />
By then the copper-shell was used sollely for the fast turbulent heating by firing a 25uF and up to 20kV for a steep-rising heating pulse at any presetable time duplicating the current(30->60kA) for ~10us. This thecnic allowed up to 1keV plasmas.<br />
<br />
Prior to the main discharges Tortur was "cleaned" by creating a glow discharge with the RF generator, heating the vessel up to 180ºC and producing small discharges with a low toroidal field (~50 mT) to outgas the vessel from impurities.<br />
<br />
It is worth to mentioned that all aquisition systems was based on CAMAC boards (5 crates) controlled by a PDP 11/23 Digital Inc. mainframe computer (-1988) and all data from the transient recorders being backuped on tape.<br />
<br />
===ISTTOK@XX===<br />
After the commissioning in Portugal, Tortur became the IST TOKamak, ISTTOK. During XX century is was operated with two capacitors banks as it's predecessor and only with forward current. The main systems have been updated, namely the vacuum systems, power supplies, the plant control systems and data acquisition.<br />
Discharges were started based on a cold plasma generated by the TORTUR RF generator (1.7MHz) but due to the high noise have been soon replaced by an electron beam source (80 eV, tungsten filament) situated on the high field side close to the SOL. The hot plasma was started by the high voltage bank (1-5kV, 1mF, 2-3ms) and then an electrolytic bank (0.4F, 350V, 40-50ms) took over.<br />
<br />
<br />
==Main components==<br />
====Innovative features===<br />
ISTTOK were since the beginning equiped with a tunnable toroidal field in view of ajusting the cyclotronic frequency to a desired value. This was quite uncommon in such class of tokamaks were the toroidal field was basically imposed either by a fixed transformer ratio from the grid or by using a capacitor bank. Conversily, due to the lack off avaiable power in campus, toroidal field had to be limited to ~0.5T.<br />
<br />
After a first exploitation phase with very similar Tortur parameters except for the toroidal field, ISTTOK@XXI became the first tokamak eqquiped with a switched IGBT primary circuit with a considerable larger capacitor bank (3.8F), allowing multiple AC discharges.<br />
<br />
ISTTOK is one of the few fusion devices eqquiped with an heavy ion beam diagnostic.<br />
<br />
===Toroidal field===<br />
====Geometry====<br />
====Current supply====<br />
<br />
===Poloidal fields===<br />
====Geometry====<br />
====Power amplifiers====<br />
<br />
===Vessel===<br />
<br />
===Vacuum system===<br />
<br />
===Gas injection===<br />
<br />
====Background pressure====<br />
<br />
====Gas puffing====<br />
<br />
====Residual gas analyser====<br />
<br />
====Broadband spectrometer====<br />
<br />
==References==<br />
<br />
==Links==<br />
[[Training]]</div>Isttok-adminhttps://isttok.tecnico.ulisboa.pt/~isttok.daemon/index.php?title=Training&diff=50Training2018-04-20T18:22:52Z<p>Isttok-admin: /* Schedule */</p>
<hr />
<div>We offer at ISTTOK several training programs from short programs till PhDs in Physics Engineering.<br />
<br />
==Short training==<br />
The short training programs normally follow the IST [http://plasmasurf.tecnico.ulisboa.pt/ PlasmaSurf] summer scholl and is a 2-week internship on ''Tokamak Engineering and Operation''. This internship take place at ISTTOK premises in IST Alameda campus, Lisbon.<br />
===Objectives===<br />
The proposed research activity is oriented to develop experimental skills in tokamak engineering and operation. It will be based on live training actions and morning courses. During the courses, the trainees will become acquainted with most diagnostics and techniques for tokamak operation and control algorithms for assisted discharges. Those courses will be complemented with practical sessions on ISTTOK, in view of the discharge set-up and plasma performance evaluation.<br />
<br />
The course focus on engineering aspects, namely on the actuators such as the power supplies, gas inlet systems, vacuum grading and technical diagnostics. A general introduction to some popular diagnostics systems will be addressed both theoretically and practical, covering magnetic probes, Langmuir probes, spectroscopy, tomography, bolometry, interferometry and residual gas-analyzer techniques.<br />
<br />
Those students need to provide (i) evidence to study in the field of nuclear fusion (Master or PhD), (ii) a recommendation letter from a scholar in the field and (iii) a motivation letter.<br />
<br />
Only accommodation and travel will be granted during the training. No stipend and meals are due per participant.<br />
<br />
===Schedule===<br />
<br />
{| class="wikitable"<br />
|+Week1<br />
|-<br />
|Time\Day <br />
|Monday<br />
|Tuesday<br />
|Wednesday<br />
|Thursday<br />
|Friday<br />
|-<br />
|rowspan="2"|9h<br />
|Content 1<br />
|Content 2<br />
|-<br />
|''H. Fernandes''<br />
|''B. Carvalho'' <br />
||rowspan="2"|14h<br />
|}</div>Isttok-adminhttps://isttok.tecnico.ulisboa.pt/~isttok.daemon/index.php?title=Training&diff=48Training2018-04-20T18:22:13Z<p>Isttok-admin: /* Short training */</p>
<hr />
<div>We offer at ISTTOK several training programs from short programs till PhDs in Physics Engineering.<br />
<br />
==Short training==<br />
The short training programs normally follow the IST [http://plasmasurf.tecnico.ulisboa.pt/ PlasmaSurf] summer scholl and is a 2-week internship on ''Tokamak Engineering and Operation''. This internship take place at ISTTOK premises in IST Alameda campus, Lisbon.<br />
===Objectives===<br />
The proposed research activity is oriented to develop experimental skills in tokamak engineering and operation. It will be based on live training actions and morning courses. During the courses, the trainees will become acquainted with most diagnostics and techniques for tokamak operation and control algorithms for assisted discharges. Those courses will be complemented with practical sessions on ISTTOK, in view of the discharge set-up and plasma performance evaluation.<br />
<br />
The course focus on engineering aspects, namely on the actuators such as the power supplies, gas inlet systems, vacuum grading and technical diagnostics. A general introduction to some popular diagnostics systems will be addressed both theoretically and practical, covering magnetic probes, Langmuir probes, spectroscopy, tomography, bolometry, interferometry and residual gas-analyzer techniques.<br />
<br />
Those students need to provide (i) evidence to study in the field of nuclear fusion (Master or PhD), (ii) a recommendation letter from a scholar in the field and (iii) a motivation letter.<br />
<br />
Only accommodation and travel will be granted during the training. No stipend and meals are due per participant.<br />
<br />
===Schedule===<br />
<br />
{| class="wikitable"<br />
|+Week1<br />
|-<br />
|Time\Day <br />
|Monday<br />
|Tuesday<br />
|Wednesday<br />
|Thursday<br />
|Friday<br />
|-<br />
||rowspan="2"|9h<br />
|Content 1<br />
|Content 2<br />
|-<br />
|''H. Fernandes''<br />
|''B. Carvalho'' <br />
||rowspan="2"|14h<br />
|}</div>Isttok-adminhttps://isttok.tecnico.ulisboa.pt/~isttok.daemon/index.php?title=Training&diff=46Training2018-04-20T18:10:11Z<p>Isttok-admin: Criou a página com "We offer at ISTTOK several training programs from short programs till PhDs in Physics Engineering. ==Short training== The short training programs normally follow the IST [h..."</p>
<hr />
<div>We offer at ISTTOK several training programs from short programs till PhDs in Physics Engineering.<br />
<br />
==Short training==<br />
The short training programs normally follow the IST [http://plasmasurf.tecnico.ulisboa.pt/ PlasmaSurf] summer scholl and is a 2-week internship on ''Tokamak Engineering and Operation''. This internship take place at ISTTOK premises in IST Alameda campus, Lisbon.<br />
<br />
The proposed research activity is oriented to develop experimental skills in tokamak engineering and operation. It will be based on live training actions and morning courses. During the courses, the trainees will become acquainted with most diagnostics and techniques for tokamak operation and control algorithms for assisted discharges. Those courses will be complemented with practical sessions on ISTTOK, in view of the discharge set-up and plasma performance evaluation.<br />
<br />
The course focus on engineering aspects, namely on the actuators such as the power supplies, gas inlet systems, vacuum grading and technical diagnostics. A general introduction to some popular diagnostics systems will be addressed both theoretically and practical, covering magnetic probes, Langmuir probes, spectroscopy, tomography, bolometry, interferometry and residual gas-analyzer techniques.<br />
<br />
Those students need to provide (i) evidence to study in the field of nuclear fusion (Master or PhD), (ii) a recommendation letter from a scholar in the field and (iii) a motivation letter.<br />
<br />
Only accommodation and travel will be granted during the training. No stipend and meals are due per participant.</div>Isttok-adminhttps://isttok.tecnico.ulisboa.pt/~isttok.daemon/index.php?title=ISTTOK_-_Wiki&diff=44ISTTOK - Wiki2018-04-20T18:02:19Z<p>Isttok-admin: </p>
<hr />
<div><strong>IST Tokamak - ISTTOK</strong><br />
<br />
=Description=<br />
<br />
The ISTTOK Tokamak ("Instituto Superior Técnico TOKamak") is a research fusion reactor located at Instituto Superior Técnico.<br />
<br />
It has a circular cross-section due to a poloidal graphite limiter and an iron core transformer. This magnetic confinement experiment has been built from some components (supporting structure, vacuum chamber, copper shell, transformer, toroidal magnetic field coils, radio-frequency generator, and capacitor banks) of the precessor TORTUR tokamak which was de-commissioned by the Association EURATOM/FOM in 1988.<br />
<br />
[[File:Isttok.jpg]]<br />
==Goals and research objectives==<br />
The scientific programme has been based on: <br />
* Edge plasma turbulence studies;<br />
* Operation and control on alternating plasma current regimes; <br />
* Testing of liquid metal limiter concept; <br />
* Development and upgrade of diagnostics; <br />
* Test bed facility for new data acquisition concepts and hardware.<br />
===Theory contribution===<br />
Understanding turbulent transport is important to optimize the plasma confinement and for predicting the performance of future devices. Research on the comprehensive investigation of the multi-scale physics aspects of the edge turbulence, from its origin to the impact on transport including plasma-wall interaction. ISTTOK is ideal for edge physics studies due to its flexibility, low operation costs, short time scale for diagnostics implementation and compatibility with electrostatic probes. The universality of several edge physics phenomena was verified in different devices, confirming the relevance of these studies in small devices. Present activities include: <br />
*Contribute to a better understanding of spontaneously generated large-scale sheared flows and its role in regulating plasma transport.<br />
*Characterize and control the SOL intermittent transport.<br />
*Develop different electrical probes systems for edge studies.<br />
*Provide synergies between theory and experimental groups working on edge/SOL physics.<br />
*Develop analysis tools required to process the massive experimental data obtained . <br />
<br />
===Diagnostics development===<br />
<br />
Further studies on the ISTTOK plasma emissivity reconstruction using analytical methods, aiming at the best choice for real-time implementation in ISTTOK.<br />
Upgrade existing tomographic cameras to 3 x 16 channels in order to improve spatial resolution for enhanced emissivity reconstruction.<br />
Developing and building a retarding electrostatic field cylindrical energy analyzer (CEA) to measure plasma potentials in the core and their fluctuations. <br />
<br />
===Main achievements===<br />
<br />
====AC operation====<br />
Due to iron core saturation, operation of ISTTOK in single pulse mode is limited to 35 ms plasma duration. ISTTOK has suffer a major update of its control systems and power supplies to operate in AC mode increasing that parameter to more than 1000 ms. Within this line of research present activities include:<br />
*Operation of the tokamak ISTTOK in a multi-cycle alternating plasma current regime, to obtain long duration discharges.<br />
*Implementation of a real-time plasma control system and study of the control of long duration AC discharges in ISTTOK.<br />
*Development of advanced gas feed control to improve reproducible and reliable plasmas with high performance.<br />
Testing of liquid metal PFC<br />
<br />
====Liquid metals as PFCs====<br />
One of the most challenging issues with regards to the operation of a future fusion reactor is related to plasma-wall interaction. Solid materials exposed to fusion plasmas are known to suffer significant damage that reduces wall lifetime. Liquid metals have proven to be of relevance for PFC protection. Due to ISTTOK characteristics its programme has also focused on testing liquid metals PFC´s and their properties:<br />
*Develop a novel Liquid Metal Limiter based on micro-channels structures.<br />
*Build and test the new LML concept using gallium as liquid metal.<br />
*Expose this PFC to ISTTOK plasmas.<br />
*Study the behavior of the limiter surface temperature increase with liquid metal re-circulation.<br />
<br />
===Data acquisition and control===<br />
Implementation of a control system based on an optimized state-space model for real time control of the plasma current magnitude and centroid position retrieved by a twelve mirnov coils poloidal set.<br />
<br />
==Physical parameters==<br />
==Nominal plasma parameters==<br />
==Precedents==<br />
===TORTUR===<br />
Tortur was a tokamak designed in Grenoble with an initial primary to secondary winding ratio of 1:1. It starts to operate in 1974 at the FOM institute at Nieuwegein on the Neederlands.<br />
<br />
For the primary was used the stabilizing cooper-shell structure. A very high current had to be feed in this primary and short discharges were obtained (up to 8 ms). The vessel was a glass-quartz type.<br />
It's name origin was due to the acronym TORus for TURbulent heating. The underlying idea was to generate a suficient large current through the plasma to the limit were micro-instabilites will be excited enhancing the plasma resistivity and allowing further ohmic-heating.<br />
<br />
===TORTUR II===<br />
Tortur was not capable to diagnose properly the heated plasma and the high primary voltage needed posed severe insulation problems. In 1978 it undergoes a major upgrade. A new stainless steel 625 vessel was installed being divided in two C-sections and equiped with 33 ports of 35mm, constructed by Avica Equipment, England. Basically the vessel were made based on port structures welded together by a thin inconnel bellow of 0.15mm with an inner diameter of 200mm. Such thin metal structure allowed for a suficient fast penetration of the electric fiels used for the turbulent heating.<br />
<br />
===TORTUR III===<br />
By 1981 Tortur undergo again a vessel upgrade of the former one by the same manufacturer, assuming the actual design as in ISTTOK . A higher toroidal magnetic field was comissioned to improve confinement (up to 5T) in paralell with a structural reinforcement. Besides that it was equipped with a iron-core transformer yoke switchable in a 20:1 or 40:1 ratio, allowing to extend plasma discharges up to 50 ms. This pulse extension was possible as well by the instalation of a quadrupole for creating the necessary vertical and horizontal magnetic fields for plasma stability, centering the plasma in the chamber.<br />
<br />
By then the copper-shell was used sollely for the fast turbulent heating by firing a 25uF and up to 20kV for a steep-rising heating pulse at any presetable time duplicating the current(30->60kA) for ~10us. This thecnic allowed up to 1keV plasmas.<br />
<br />
Prior to the main discharges Tortur was "cleaned" by creating a glow discharge with the RF generator, heating the vessel up to 180ºC and producing small discharges with a low toroidal field (~50 mT) to outgas the vessel from impurities.<br />
<br />
It is worth to mentioned that all aquisition systems was based on CAMAC boards (5 crates) controlled by a PDP 11/23 Digital Inc. mainframe computer (-1988) and all data from the transient recorders being backuped on tape.<br />
<br />
===ISTTOK@XX===<br />
After the commissioning in Portugal, Tortur became the IST TOKamak, ISTTOK. During XX century is was operated with two capacitors banks as it's predecessor and only with forward current. The main systems have been updated, namely the vacuum systems, power supplies, the plant control systems and data acquisition.<br />
Discharges were started based on a cold plasma generated by the TORTUR RF generator (1.7MHz) but due to the high noise have been soon replaced by an electron beam source (80 eV, tungsten filament) situated on the high field side close to the SOL. The hot plasma was started by the high voltage bank (1-5kV, 1mF, 2-3ms) and then an electrolytic bank (0.4F, 350V, 40-50ms) took over.<br />
<br />
<br />
==Main components==<br />
<br />
<br />
==References==<br />
<br />
==Links==<br />
[[Training]]</div>Isttok-adminhttps://isttok.tecnico.ulisboa.pt/~isttok.daemon/index.php?title=ISTTOK_-_Wiki&diff=42ISTTOK - Wiki2018-04-20T17:53:02Z<p>Isttok-admin: /* Onde começar */</p>
<hr />
<div><strong>IST Tokamak - ISTTOK</strong><br />
<br />
=Description=<br />
<br />
The ISTTOK Tokamak ("Instituto Superior Técnico TOKamak") is a research fusion reactor located at Instituto Superior Técnico.<br />
<br />
It has a circular cross-section due to a poloidal graphite limiter and an iron core transformer. This magnetic confinement experiment has been built from some components (supporting structure, vacuum chamber, copper shell, transformer, toroidal magnetic field coils, radio-frequency generator, and capacitor banks) of the precessor TORTUR tokamak which was de-commissioned by the Association EURATOM/FOM in 1988.<br />
<br />
[[File:Isttok.jpg]]<br />
==Goals and research objectives==<br />
The scientific programme has been based on: <br />
* Edge plasma turbulence studies;<br />
* Operation and control on alternating plasma current regimes; <br />
* Testing of liquid metal limiter concept; <br />
* Development and upgrade of diagnostics; <br />
* Test bed facility for new data acquisition concepts and hardware.<br />
===Theory contribution===<br />
Understanding turbulent transport is important to optimize the plasma confinement and for predicting the performance of future devices. Research on the comprehensive investigation of the multi-scale physics aspects of the edge turbulence, from its origin to the impact on transport including plasma-wall interaction. ISTTOK is ideal for edge physics studies due to its flexibility, low operation costs, short time scale for diagnostics implementation and compatibility with electrostatic probes. The universality of several edge physics phenomena was verified in different devices, confirming the relevance of these studies in small devices. Present activities include: <br />
*Contribute to a better understanding of spontaneously generated large-scale sheared flows and its role in regulating plasma transport.<br />
*Characterize and control the SOL intermittent transport.<br />
*Develop different electrical probes systems for edge studies.<br />
*Provide synergies between theory and experimental groups working on edge/SOL physics.<br />
*Develop analysis tools required to process the massive experimental data obtained . <br />
<br />
===Diagnostics development===<br />
<br />
Further studies on the ISTTOK plasma emissivity reconstruction using analytical methods, aiming at the best choice for real-time implementation in ISTTOK.<br />
Upgrade existing tomographic cameras to 3 x 16 channels in order to improve spatial resolution for enhanced emissivity reconstruction.<br />
Developing and building a retarding electrostatic field cylindrical energy analyzer (CEA) to measure plasma potentials in the core and their fluctuations. <br />
<br />
===Main achievements===<br />
<br />
====AC operation====<br />
Due to iron core saturation, operation of ISTTOK in single pulse mode is limited to 35 ms plasma duration. ISTTOK has suffer a major update of its control systems and power supplies to operate in AC mode increasing that parameter to more than 1000 ms. Within this line of research present activities include:<br />
*Operation of the tokamak ISTTOK in a multi-cycle alternating plasma current regime, to obtain long duration discharges.<br />
*Implementation of a real-time plasma control system and study of the control of long duration AC discharges in ISTTOK.<br />
*Development of advanced gas feed control to improve reproducible and reliable plasmas with high performance.<br />
Testing of liquid metal PFC<br />
<br />
====Liquid metals as PFCs====<br />
One of the most challenging issues with regards to the operation of a future fusion reactor is related to plasma-wall interaction. Solid materials exposed to fusion plasmas are known to suffer significant damage that reduces wall lifetime. Liquid metals have proven to be of relevance for PFC protection. Due to ISTTOK characteristics its programme has also focused on testing liquid metals PFC´s and their properties:<br />
*Develop a novel Liquid Metal Limiter based on micro-channels structures.<br />
*Build and test the new LML concept using gallium as liquid metal.<br />
*Expose this PFC to ISTTOK plasmas.<br />
*Study the behavior of the limiter surface temperature increase with liquid metal re-circulation.<br />
<br />
===Data acquisition and control===<br />
Implementation of a control system based on an optimized state-space model for real time control of the plasma current magnitude and centroid position retrieved by a twelve mirnov coils poloidal set.<br />
<br />
==Physical parameters==<br />
==Nominal plasma parameters==<br />
==Precedents==<br />
===TORTUR===<br />
Tortur was a tokamak designed in Grenoble with an initial primary to secondary winding ratio of 1:1. It starts to operate in 1974 at the FOM institute at Nieuwegein on the Neederlands.<br />
<br />
For the primary was used the stabilizing cooper-shell structure. A very high current had to be feed in this primary and short discharges were obtained (up to 8 ms). The vessel was a glass-quartz type.<br />
It's name origin was due to the acronym TORus for TURbulent heating. The underlying idea was to generate a suficient large current through the plasma to the limit were micro-instabilites will be excited enhancing the plasma resistivity and allowing further ohmic-heating.<br />
<br />
===TORTUR II===<br />
Tortur was not capable to diagnose properly the heated plasma and the high primary voltage needed posed severe insulation problems. In 1978 it undergoes a major upgrade. A new stainless steel 625 vessel was installed being divided in two C-sections and equiped with 33 ports of 35mm, constructed by Avica Equipment, England. Basically the vessel were made based on port structures welded together by a thin inconnel bellow of 0.15mm with an inner diameter of 200mm. Such thin metal structure allowed for a suficient fast penetration of the electric fiels used for the turbulent heating.<br />
<br />
===TORTUR III===<br />
By 1981 Tortur undergo again a vessel upgrade of the former one by the same manufacturer, assuming the actual design as in ISTTOK . A higher toroidal magnetic field was comissioned to improve confinement (up to 5T) in paralell with a structural reinforcement. Besides that it was equipped with a iron-core transformer yoke switchable in a 20:1 or 40:1 ratio, allowing to extend plasma discharges up to 50 ms. This pulse extension was possible as well by the instalation of a quadrupole for creating the necessary vertical and horizontal magnetic fields for plasma stability, centering the plasma in the chamber.<br />
<br />
By then the copper-shell was used sollely for the fast turbulent heating by firing a 25uF and up to 20kV for a steep-rising heating pulse at any presetable time duplicating the current(30->60kA) for ~10us. This thecnic allowed up to 1keV plasmas.<br />
<br />
Prior to the main discharges Tortur was "cleaned" by creating a glow discharge with the RF generator, heating the vessel up to 180ºC and producing small discharges with a low toroidal field (~50 mT) to outgas the vessel from impurities.<br />
<br />
It is worth to mentioned that all aquisition systems was based on CAMAC boards (5 crates) controlled by a PDP 11/23 Digital Inc. mainframe computer (-1988) and all data from the transient recorders being backuped on tape.<br />
<br />
===ISTTOK@XX===<br />
After the commissioning in Portugal, Tortur became the IST TOKamak, ISTTOK. During XX century is was operated with two capacitors banks as it's predecessor and only with forward current. The main systems have been updated, namely the vacuum systems, power supplies, the plant control systems and data acquisition.<br />
Discharges were started based on a cold plasma generated by the TORTUR RF generator (1.7MHz) but due to the high noise have been soon replaced by an electron beam source (80 eV, tungsten filament) situated on the high field side close to the SOL. The hot plasma was started by the high voltage bank (1-5kV, 1mF, 2-3ms) and then an electrolytic bank (0.4F, 350V, 40-50ms) took over.<br />
<br />
<br />
==Main components==<br />
<br />
<br />
==References==</div>Isttok-adminhttps://isttok.tecnico.ulisboa.pt/~isttok.daemon/index.php?title=ISTTOK_-_Wiki&diff=40ISTTOK - Wiki2018-04-20T17:46:36Z<p>Isttok-admin: /* TORTUR II */</p>
<hr />
<div><strong>IST Tokamak - ISTTOK</strong><br />
<br />
=Description=<br />
<br />
The ISTTOK Tokamak ("Instituto Superior Técnico TOKamak") is a research fusion reactor located at Instituto Superior Técnico.<br />
<br />
It has a circular cross-section due to a poloidal graphite limiter and an iron core transformer. This magnetic confinement experiment has been built from some components (supporting structure, vacuum chamber, copper shell, transformer, toroidal magnetic field coils, radio-frequency generator, and capacitor banks) of the precessor TORTUR tokamak which was de-commissioned by the Association EURATOM/FOM in 1988.<br />
<br />
[[File:Isttok.jpg]]<br />
==Goals and research objectives==<br />
The scientific programme has been based on: <br />
* Edge plasma turbulence studies;<br />
* Operation and control on alternating plasma current regimes; <br />
* Testing of liquid metal limiter concept; <br />
* Development and upgrade of diagnostics; <br />
* Test bed facility for new data acquisition concepts and hardware.<br />
===Theory contribution===<br />
Understanding turbulent transport is important to optimize the plasma confinement and for predicting the performance of future devices. Research on the comprehensive investigation of the multi-scale physics aspects of the edge turbulence, from its origin to the impact on transport including plasma-wall interaction. ISTTOK is ideal for edge physics studies due to its flexibility, low operation costs, short time scale for diagnostics implementation and compatibility with electrostatic probes. The universality of several edge physics phenomena was verified in different devices, confirming the relevance of these studies in small devices. Present activities include: <br />
*Contribute to a better understanding of spontaneously generated large-scale sheared flows and its role in regulating plasma transport.<br />
*Characterize and control the SOL intermittent transport.<br />
*Develop different electrical probes systems for edge studies.<br />
*Provide synergies between theory and experimental groups working on edge/SOL physics.<br />
*Develop analysis tools required to process the massive experimental data obtained . <br />
<br />
===Diagnostics development===<br />
<br />
Further studies on the ISTTOK plasma emissivity reconstruction using analytical methods, aiming at the best choice for real-time implementation in ISTTOK.<br />
Upgrade existing tomographic cameras to 3 x 16 channels in order to improve spatial resolution for enhanced emissivity reconstruction.<br />
Developing and building a retarding electrostatic field cylindrical energy analyzer (CEA) to measure plasma potentials in the core and their fluctuations. <br />
<br />
===Main achievements===<br />
<br />
====AC operation====<br />
Due to iron core saturation, operation of ISTTOK in single pulse mode is limited to 35 ms plasma duration. ISTTOK has suffer a major update of its control systems and power supplies to operate in AC mode increasing that parameter to more than 1000 ms. Within this line of research present activities include:<br />
*Operation of the tokamak ISTTOK in a multi-cycle alternating plasma current regime, to obtain long duration discharges.<br />
*Implementation of a real-time plasma control system and study of the control of long duration AC discharges in ISTTOK.<br />
*Development of advanced gas feed control to improve reproducible and reliable plasmas with high performance.<br />
Testing of liquid metal PFC<br />
<br />
====Liquid metals as PFCs====<br />
One of the most challenging issues with regards to the operation of a future fusion reactor is related to plasma-wall interaction. Solid materials exposed to fusion plasmas are known to suffer significant damage that reduces wall lifetime. Liquid metals have proven to be of relevance for PFC protection. Due to ISTTOK characteristics its programme has also focused on testing liquid metals PFC´s and their properties:<br />
*Develop a novel Liquid Metal Limiter based on micro-channels structures.<br />
*Build and test the new LML concept using gallium as liquid metal.<br />
*Expose this PFC to ISTTOK plasmas.<br />
*Study the behavior of the limiter surface temperature increase with liquid metal re-circulation.<br />
<br />
===Data acquisition and control===<br />
Implementation of a control system based on an optimized state-space model for real time control of the plasma current magnitude and centroid position retrieved by a twelve mirnov coils poloidal set.<br />
<br />
==Physical parameters==<br />
==Nominal plasma parameters==<br />
==Precedents==<br />
===TORTUR===<br />
Tortur was a tokamak designed in Grenoble with an initial primary to secondary winding ratio of 1:1. It starts to operate in 1974 at the FOM institute at Nieuwegein on the Neederlands.<br />
<br />
For the primary was used the stabilizing cooper-shell structure. A very high current had to be feed in this primary and short discharges were obtained (up to 8 ms). The vessel was a glass-quartz type.<br />
It's name origin was due to the acronym TORus for TURbulent heating. The underlying idea was to generate a suficient large current through the plasma to the limit were micro-instabilites will be excited enhancing the plasma resistivity and allowing further ohmic-heating.<br />
<br />
===TORTUR II===<br />
Tortur was not capable to diagnose properly the heated plasma and the high primary voltage needed posed severe insulation problems. In 1978 it undergoes a major upgrade. A new stainless steel 625 vessel was installed being divided in two C-sections and equiped with 33 ports of 35mm, constructed by Avica Equipment, England. Basically the vessel were made based on port structures welded together by a thin inconnel bellow of 0.15mm with an inner diameter of 200mm. Such thin metal structure allowed for a suficient fast penetration of the electric fiels used for the turbulent heating.<br />
<br />
===TORTUR III===<br />
By 1981 Tortur undergo again a vessel upgrade of the former one by the same manufacturer, assuming the actual design as in ISTTOK . A higher toroidal magnetic field was comissioned to improve confinement (up to 5T) in paralell with a structural reinforcement. Besides that it was equipped with a iron-core transformer yoke switchable in a 20:1 or 40:1 ratio, allowing to extend plasma discharges up to 50 ms. This pulse extension was possible as well by the instalation of a quadrupole for creating the necessary vertical and horizontal magnetic fields for plasma stability, centering the plasma in the chamber.<br />
<br />
By then the copper-shell was used sollely for the fast turbulent heating by firing a 25uF and up to 20kV for a steep-rising heating pulse at any presetable time duplicating the current(30->60kA) for ~10us. This thecnic allowed up to 1keV plasmas.<br />
<br />
Prior to the main discharges Tortur was "cleaned" by creating a glow discharge with the RF generator, heating the vessel up to 180ºC and producing small discharges with a low toroidal field (~50 mT) to outgas the vessel from impurities.<br />
<br />
It is worth to mentioned that all aquisition systems was based on CAMAC boards (5 crates) controlled by a PDP 11/23 Digital Inc. mainframe computer (-1988) and all data from the transient recorders being backuped on tape.<br />
<br />
===ISTTOK@XX===<br />
After the commissioning in Portugal, Tortur became the IST TOKamak, ISTTOK. During XX century is was operated with two capacitors banks as it's predecessor and only with forward current. The main systems have been updated, namely the vacuum systems, power supplies, the plant control systems and data acquisition.<br />
Discharges were started based on a cold plasma generated by the TORTUR RF generator (1.7MHz) but due to the high noise have been soon replaced by an electron beam source (80 eV, tungsten filament) situated on the high field side close to the SOL. The hot plasma was started by the high voltage bank (1-5kV, 1mF, 2-3ms) and then an electrolytic bank (0.4F, 350V, 40-50ms) took over.<br />
<br />
<br />
==Main components==<br />
<br />
<br />
== Onde começar ==<br />
<br />
* [[ISTTOK]]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Manual:FAQ Perguntas e respostas frequentes sobre o MediaWiki]<br />
* [https://lists.wikimedia.org/mailman/listinfo/mediawiki-announce Subscreva a lista de divulgação de novas versões do MediaWiki]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Localisation#Translation_resources Regionalize o MediaWiki para a sua língua]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Manual:Combating_spam Aprenda a combater <i>spam</i> na sua wiki]</div>Isttok-adminhttps://isttok.tecnico.ulisboa.pt/~isttok.daemon/index.php?title=ISTTOK_-_Wiki&diff=38ISTTOK - Wiki2018-04-20T17:43:53Z<p>Isttok-admin: /* Description */</p>
<hr />
<div><strong>IST Tokamak - ISTTOK</strong><br />
<br />
=Description=<br />
<br />
The ISTTOK Tokamak ("Instituto Superior Técnico TOKamak") is a research fusion reactor located at Instituto Superior Técnico.<br />
<br />
It has a circular cross-section due to a poloidal graphite limiter and an iron core transformer. This magnetic confinement experiment has been built from some components (supporting structure, vacuum chamber, copper shell, transformer, toroidal magnetic field coils, radio-frequency generator, and capacitor banks) of the precessor TORTUR tokamak which was de-commissioned by the Association EURATOM/FOM in 1988.<br />
<br />
[[File:Isttok.jpg]]<br />
==Goals and research objectives==<br />
The scientific programme has been based on: <br />
* Edge plasma turbulence studies;<br />
* Operation and control on alternating plasma current regimes; <br />
* Testing of liquid metal limiter concept; <br />
* Development and upgrade of diagnostics; <br />
* Test bed facility for new data acquisition concepts and hardware.<br />
===Theory contribution===<br />
Understanding turbulent transport is important to optimize the plasma confinement and for predicting the performance of future devices. Research on the comprehensive investigation of the multi-scale physics aspects of the edge turbulence, from its origin to the impact on transport including plasma-wall interaction. ISTTOK is ideal for edge physics studies due to its flexibility, low operation costs, short time scale for diagnostics implementation and compatibility with electrostatic probes. The universality of several edge physics phenomena was verified in different devices, confirming the relevance of these studies in small devices. Present activities include: <br />
*Contribute to a better understanding of spontaneously generated large-scale sheared flows and its role in regulating plasma transport.<br />
*Characterize and control the SOL intermittent transport.<br />
*Develop different electrical probes systems for edge studies.<br />
*Provide synergies between theory and experimental groups working on edge/SOL physics.<br />
*Develop analysis tools required to process the massive experimental data obtained . <br />
<br />
===Diagnostics development===<br />
<br />
Further studies on the ISTTOK plasma emissivity reconstruction using analytical methods, aiming at the best choice for real-time implementation in ISTTOK.<br />
Upgrade existing tomographic cameras to 3 x 16 channels in order to improve spatial resolution for enhanced emissivity reconstruction.<br />
Developing and building a retarding electrostatic field cylindrical energy analyzer (CEA) to measure plasma potentials in the core and their fluctuations. <br />
<br />
===Main achievements===<br />
<br />
====AC operation====<br />
Due to iron core saturation, operation of ISTTOK in single pulse mode is limited to 35 ms plasma duration. ISTTOK has suffer a major update of its control systems and power supplies to operate in AC mode increasing that parameter to more than 1000 ms. Within this line of research present activities include:<br />
*Operation of the tokamak ISTTOK in a multi-cycle alternating plasma current regime, to obtain long duration discharges.<br />
*Implementation of a real-time plasma control system and study of the control of long duration AC discharges in ISTTOK.<br />
*Development of advanced gas feed control to improve reproducible and reliable plasmas with high performance.<br />
Testing of liquid metal PFC<br />
<br />
====Liquid metals as PFCs====<br />
One of the most challenging issues with regards to the operation of a future fusion reactor is related to plasma-wall interaction. Solid materials exposed to fusion plasmas are known to suffer significant damage that reduces wall lifetime. Liquid metals have proven to be of relevance for PFC protection. Due to ISTTOK characteristics its programme has also focused on testing liquid metals PFC´s and their properties:<br />
*Develop a novel Liquid Metal Limiter based on micro-channels structures.<br />
*Build and test the new LML concept using gallium as liquid metal.<br />
*Expose this PFC to ISTTOK plasmas.<br />
*Study the behavior of the limiter surface temperature increase with liquid metal re-circulation.<br />
<br />
===Data acquisition and control===<br />
Implementation of a control system based on an optimized state-space model for real time control of the plasma current magnitude and centroid position retrieved by a twelve mirnov coils poloidal set.<br />
<br />
==Physical parameters==<br />
==Nominal plasma parameters==<br />
==Precedents==<br />
===TORTUR===<br />
Tortur was a tokamak designed in Grenoble with an initial primary to secondary winding ratio of 1:1. It starts to operate in 1974 at the FOM institute at Nieuwegein on the Neederlands.<br />
<br />
For the primary was used the stabilizing cooper-shell structure. A very high current had to be feed in this primary and short discharges were obtained (up to 8 ms). The vessel was a glass-quartz type.<br />
It's name origin was due to the acronym TORus for TURbulent heating. The underlying idea was to generate a suficient large current through the plasma to the limit were micro-instabilites will be excited enhancing the plasma resistivity and allowing further ohmic-heating.<br />
<br />
===TORTUR II===<br />
Tortur was not capable to diagnose properly the heated plasma and the high primary voltage need poses insulation problems. In 1978 it undergoes a major upgrade. A new stainless steel 625 vessel was installed being divided in two C-sections and equiped with 33 ports of 35mm, constructed by Avica Equipment, England. Basically the vessel were made based on port structures welded together by a thin inconnel bellow of 0.15mm with an inner diameter of 200mm. Such thin metal structure alloed for a suficient fast penetration of the electric fiels used for the turbulent heating.<br />
<br />
<br />
===TORTUR III===<br />
By 1981 Tortur undergo again a vessel upgrade of the former one by the same manufacturer, assuming the actual design as in ISTTOK . A higher toroidal magnetic field was comissioned to improve confinement (up to 5T) in paralell with a structural reinforcement. Besides that it was equipped with a iron-core transformer yoke switchable in a 20:1 or 40:1 ratio, allowing to extend plasma discharges up to 50 ms. This pulse extension was possible as well by the instalation of a quadrupole for creating the necessary vertical and horizontal magnetic fields for plasma stability, centering the plasma in the chamber.<br />
<br />
By then the copper-shell was used sollely for the fast turbulent heating by firing a 25uF and up to 20kV for a steep-rising heating pulse at any presetable time duplicating the current(30->60kA) for ~10us. This thecnic allowed up to 1keV plasmas.<br />
<br />
Prior to the main discharges Tortur was "cleaned" by creating a glow discharge with the RF generator, heating the vessel up to 180ºC and producing small discharges with a low toroidal field (~50 mT) to outgas the vessel from impurities.<br />
<br />
It is worth to mentioned that all aquisition systems was based on CAMAC boards (5 crates) controlled by a PDP 11/23 Digital Inc. mainframe computer (-1988) and all data from the transient recorders being backuped on tape.<br />
<br />
===ISTTOK@XX===<br />
After the commissioning in Portugal, Tortur became the IST TOKamak, ISTTOK. During XX century is was operated with two capacitors banks as it's predecessor and only with forward current. The main systems have been updated, namely the vacuum systems, power supplies, the plant control systems and data acquisition.<br />
Discharges were started based on a cold plasma generated by the TORTUR RF generator (1.7MHz) but due to the high noise have been soon replaced by an electron beam source (80 eV, tungsten filament) situated on the high field side close to the SOL. The hot plasma was started by the high voltage bank (1-5kV, 1mF, 2-3ms) and then an electrolytic bank (0.4F, 350V, 40-50ms) took over.<br />
<br />
<br />
==Main components==<br />
<br />
<br />
== Onde começar ==<br />
<br />
* [[ISTTOK]]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Manual:FAQ Perguntas e respostas frequentes sobre o MediaWiki]<br />
* [https://lists.wikimedia.org/mailman/listinfo/mediawiki-announce Subscreva a lista de divulgação de novas versões do MediaWiki]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Localisation#Translation_resources Regionalize o MediaWiki para a sua língua]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Manual:Combating_spam Aprenda a combater <i>spam</i> na sua wiki]</div>Isttok-adminhttps://isttok.tecnico.ulisboa.pt/~isttok.daemon/index.php?title=ISTTOK_-_Wiki&diff=36ISTTOK - Wiki2018-04-20T16:36:51Z<p>Isttok-admin: /* Main experimental achievements */</p>
<hr />
<div><strong>IST Tokamak - ISTTOK</strong><br />
<br />
=Description=<br />
<br />
The ISTTOK Tokamak ("Instituto Superior Técnico TOKamak") is a research fusion reactor (tokamak) of the Instituto Superior Técnico.<br />
<br />
The ISTTOK Tokamak ("Instituto Superior Tecnico TOKamak") is a research fusion reactor (tokamak) of the Instituto Superior Tecnico. It has a circular cross-section due to a poloidal graphite limiter and an iron core transformer. This magnetic confinement experiment has been built from some components (supporting structure, vacuum chamber, copper shell, transformer, toroidal magnetic field coils, radio-frequency generator, and capacitor banks) of the ex-tokamak TORTUR which was de-commissioned by the Association EURATOM/FOM in 1988.<br />
<br />
[[File:Isttok.jpg]]<br />
==Goals and research objectives==<br />
The scientific programme has been based on: <br />
* Edge plasma turbulence studies;<br />
* Operation and control on alternating plasma current regimes; <br />
* Testing of liquid metal limiter concept; <br />
* Development and upgrade of diagnostics; <br />
* Test bed facility for new data acquisition concepts and hardware.<br />
===Theory contribution===<br />
Understanding turbulent transport is important to optimize the plasma confinement and for predicting the performance of future devices. Research on the comprehensive investigation of the multi-scale physics aspects of the edge turbulence, from its origin to the impact on transport including plasma-wall interaction. ISTTOK is ideal for edge physics studies due to its flexibility, low operation costs, short time scale for diagnostics implementation and compatibility with electrostatic probes. The universality of several edge physics phenomena was verified in different devices, confirming the relevance of these studies in small devices. Present activities include: <br />
*Contribute to a better understanding of spontaneously generated large-scale sheared flows and its role in regulating plasma transport.<br />
*Characterize and control the SOL intermittent transport.<br />
*Develop different electrical probes systems for edge studies.<br />
*Provide synergies between theory and experimental groups working on edge/SOL physics.<br />
*Develop analysis tools required to process the massive experimental data obtained . <br />
<br />
===Diagnostics development===<br />
<br />
Further studies on the ISTTOK plasma emissivity reconstruction using analytical methods, aiming at the best choice for real-time implementation in ISTTOK.<br />
Upgrade existing tomographic cameras to 3 x 16 channels in order to improve spatial resolution for enhanced emissivity reconstruction.<br />
Developing and building a retarding electrostatic field cylindrical energy analyzer (CEA) to measure plasma potentials in the core and their fluctuations. <br />
===Main achievements===<br />
====AC operation====<br />
Due to iron core saturation, operation of ISTTOK in single pulse mode is limited to 35 ms plasma duration. ISTTOK has suffer a major update of its control systems and power supplies to operate in AC mode increasing that parameter to more than 1000 ms. Within this line of research present activities include:<br />
*Operation of the tokamak ISTTOK in a multi-cycle alternating plasma current regime, to obtain long duration discharges.<br />
*Implementation of a real-time plasma control system and study of the control of long duration AC discharges in ISTTOK.<br />
*Development of advanced gas feed control to improve reproducible and reliable plasmas with high performance.<br />
Testing of liquid metal PFC<br />
<br />
====Liquid metals as PFCs====<br />
One of the most challenging issues with regards to the operation of a future fusion reactor is related to plasma-wall interaction. Solid materials exposed to fusion plasmas are known to suffer significant damage that reduces wall lifetime. Liquid metals have proven to be of relevance for PFC protection. Due to ISTTOK characteristics its programme has also focused on testing liquid metals PFC´s and their properties:<br />
*Develop a novel Liquid Metal Limiter based on micro-channels structures.<br />
*Build and test the new LML concept using gallium as liquid metal.<br />
*Expose this PFC to ISTTOK plasmas.<br />
*Study the behavior of the limiter surface temperature increase with liquid metal re-circulation.<br />
<br />
===Data acquisition and control===<br />
Implementation of a control system based on an optimized state-space model for real time control of the plasma current magnitude and centroid position retrieved by a twelve mirnov coils poloidal set.<br />
<br />
==Physical parameters==<br />
==Nominal plasma parameters==<br />
==Precedents==<br />
===TORTUR===<br />
Tortur was a tokamak designed in Grenoble with an initial primary to secondary winding ratio of 1:1, as the stabilizing cooper-shell was used as well as the primary. A very high current had to be feed in this primary and short discharges were obtained (up to 8 ms). The stainless steel 625 vessel was divided in two C-sections and equiped with 33 ports of 35mm, constructed by Avica Equipment, England. Basically the vessel is port structures welded together by a thin bellow of 0.15mm with an inner diameter of 200mm<br />
<br />
===TORTUR II===<br />
Tortur II undergo a vessel upgrade of the former one by the same manufacturer, assuming the actual form os ISTTOK. Besides that was equipped with a iron-core transformer with 20:1 or 40:1 transformer relation.<br />
<br />
===ISTTOK@XX===<br />
After the commissioning in Portugal, Tortur became the IST TOKamak, ISTTOK. During XX century is was operated with two capacitors banks as it's predecessor and only with forward current. The main systems have been updated, namely the vacuum systems, the plant control systems and data acquisition.<br />
Discharges were started based on a cold plasma generated by the TORTUR RF generator but due to the high noise have been soon replaced by an electron beam source (80 eV, tungsten filament) situated on the high field side close to the SOL. The hot plasma was started by the high voltage bank (1-5kV, 100uF, 2-3ms) and then an electrolytic bank (0.8F, 350V, 40-50ms) took over.<br />
<br />
==Main components==<br />
<br />
<br />
== Onde começar ==<br />
<br />
* [[ISTTOK]]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Manual:FAQ Perguntas e respostas frequentes sobre o MediaWiki]<br />
* [https://lists.wikimedia.org/mailman/listinfo/mediawiki-announce Subscreva a lista de divulgação de novas versões do MediaWiki]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Localisation#Translation_resources Regionalize o MediaWiki para a sua língua]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Manual:Combating_spam Aprenda a combater <i>spam</i> na sua wiki]</div>Isttok-adminhttps://isttok.tecnico.ulisboa.pt/~isttok.daemon/index.php?title=ISTTOK_-_Wiki&diff=34ISTTOK - Wiki2018-04-20T14:55:54Z<p>Isttok-admin: /* Precedents */</p>
<hr />
<div><strong>IST Tokamak - ISTTOK</strong><br />
<br />
=Description=<br />
<br />
The ISTTOK Tokamak ("Instituto Superior Técnico TOKamak") is a research fusion reactor (tokamak) of the Instituto Superior Técnico.<br />
<br />
The ISTTOK Tokamak ("Instituto Superior Tecnico TOKamak") is a research fusion reactor (tokamak) of the Instituto Superior Tecnico. It has a circular cross-section due to a poloidal graphite limiter and an iron core transformer. This magnetic confinement experiment has been built from some components (supporting structure, vacuum chamber, copper shell, transformer, toroidal magnetic field coils, radio-frequency generator, and capacitor banks) of the ex-tokamak TORTUR which was de-commissioned by the Association EURATOM/FOM in 1988.<br />
<br />
[[File:Isttok.jpg]]<br />
==Goals and research objectives==<br />
The scientific programme has been based on: <br />
* Edge plasma turbulence studies;<br />
* Operation and control on alternating plasma current regimes; <br />
* Testing of liquid metal limiter concept; <br />
* Development and upgrade of diagnostics; <br />
* Test bed facility for new data acquisition concepts and hardware.<br />
===Theory contribution===<br />
Understanding turbulent transport is important to optimize the plasma confinement and for predicting the performance of future devices. Research on the comprehensive investigation of the multi-scale physics aspects of the edge turbulence, from its origin to the impact on transport including plasma-wall interaction. ISTTOK is ideal for edge physics studies due to its flexibility, low operation costs, short time scale for diagnostics implementation and compatibility with electrostatic probes. The universality of several edge physics phenomena was verified in different devices, confirming the relevance of these studies in small devices. Present activities include: <br />
*Contribute to a better understanding of spontaneously generated large-scale sheared flows and its role in regulating plasma transport.<br />
*Characterize and control the SOL intermittent transport.<br />
*Develop different electrical probes systems for edge studies.<br />
*Provide synergies between theory and experimental groups working on edge/SOL physics.<br />
*Develop analysis tools required to process the massive experimental data obtained . <br />
<br />
===Diagnostics development===<br />
<br />
Further studies on the ISTTOK plasma emissivity reconstruction using analytical methods, aiming at the best choice for real-time implementation in ISTTOK.<br />
Upgrade existing tomographic cameras to 3 x 16 channels in order to improve spatial resolution for enhanced emissivity reconstruction.<br />
Developing and building a retarding electrostatic field cylindrical energy analyzer (CEA) to measure plasma potentials in the core and their fluctuations. <br />
===Main experimental achievements===<br />
====AC operation====<br />
Due to iron core saturation, operation of ISTTOK in single pulse mode is limited to 35 ms plasma duration. ISTTOK has suffer a major update of its control systems and power supplies to operate in AC mode increasing that parameter to more than 1000 ms. Within this line of research present activities include:<br />
*Operation of the tokamak ISTTOK in a multi-cycle alternating plasma current regime, to obtain long duration discharges.<br />
*Implementation of a real-time plasma control system and study of the control of long duration AC discharges in ISTTOK.<br />
*Development of advanced gas feed control to improve reproducible and reliable plasmas with high performance.<br />
Testing of liquid metal PFC<br />
<br />
====Liquid metals as PFCs====<br />
One of the most challenging issues with regards to the operation of a future fusion reactor is related to plasma-wall interaction. Solid materials exposed to fusion plasmas are known to suffer significant damage that reduces wall lifetime. Liquid metals have proven to be of relevance for PFC protection. Due to ISTTOK characteristics its programme has also focused on testing liquid metals PFC´s and their properties:<br />
*Develop a novel Liquid Metal Limiter based on micro-channels structures.<br />
*Build and test the new LML concept using gallium as liquid metal.<br />
*Expose this PFC to ISTTOK plasmas.<br />
*Study the behavior of the limiter surface temperature increase with liquid metal re-circulation.<br />
<br />
<br />
===Data acquisition and control===<br />
Implementation of a control system based on an optimized state-space model for real time control of the plasma current magnitude and centroid position retrieved by a twelve mirnov coils poloidal set.<br />
<br />
==Physical parameters==<br />
==Nominal plasma parameters==<br />
==Precedents==<br />
===TORTUR===<br />
Tortur was a tokamak designed in Grenoble with an initial primary to secondary winding ratio of 1:1, as the stabilizing cooper-shell was used as well as the primary. A very high current had to be feed in this primary and short discharges were obtained (up to 8 ms). The stainless steel 625 vessel was divided in two C-sections and equiped with 33 ports of 35mm, constructed by Avica Equipment, England. Basically the vessel is port structures welded together by a thin bellow of 0.15mm with an inner diameter of 200mm<br />
<br />
===TORTUR II===<br />
Tortur II undergo a vessel upgrade of the former one by the same manufacturer, assuming the actual form os ISTTOK. Besides that was equipped with a iron-core transformer with 20:1 or 40:1 transformer relation.<br />
<br />
===ISTTOK@XX===<br />
After the commissioning in Portugal, Tortur became the IST TOKamak, ISTTOK. During XX century is was operated with two capacitors banks as it's predecessor and only with forward current. The main systems have been updated, namely the vacuum systems, the plant control systems and data acquisition.<br />
Discharges were started based on a cold plasma generated by the TORTUR RF generator but due to the high noise have been soon replaced by an electron beam source (80 eV, tungsten filament) situated on the high field side close to the SOL. The hot plasma was started by the high voltage bank (1-5kV, 100uF, 2-3ms) and then an electrolytic bank (0.8F, 350V, 40-50ms) took over.<br />
<br />
==Main components==<br />
<br />
<br />
== Onde começar ==<br />
<br />
* [[ISTTOK]]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Manual:FAQ Perguntas e respostas frequentes sobre o MediaWiki]<br />
* [https://lists.wikimedia.org/mailman/listinfo/mediawiki-announce Subscreva a lista de divulgação de novas versões do MediaWiki]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Localisation#Translation_resources Regionalize o MediaWiki para a sua língua]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Manual:Combating_spam Aprenda a combater <i>spam</i> na sua wiki]</div>Isttok-adminhttps://isttok.tecnico.ulisboa.pt/~isttok.daemon/index.php?title=ISTTOK_-_Wiki&diff=32ISTTOK - Wiki2018-04-20T14:55:40Z<p>Isttok-admin: /* Precedents */</p>
<hr />
<div><strong>IST Tokamak - ISTTOK</strong><br />
<br />
=Description=<br />
<br />
The ISTTOK Tokamak ("Instituto Superior Técnico TOKamak") is a research fusion reactor (tokamak) of the Instituto Superior Técnico.<br />
<br />
The ISTTOK Tokamak ("Instituto Superior Tecnico TOKamak") is a research fusion reactor (tokamak) of the Instituto Superior Tecnico. It has a circular cross-section due to a poloidal graphite limiter and an iron core transformer. This magnetic confinement experiment has been built from some components (supporting structure, vacuum chamber, copper shell, transformer, toroidal magnetic field coils, radio-frequency generator, and capacitor banks) of the ex-tokamak TORTUR which was de-commissioned by the Association EURATOM/FOM in 1988.<br />
<br />
[[File:Isttok.jpg]]<br />
==Goals and research objectives==<br />
The scientific programme has been based on: <br />
* Edge plasma turbulence studies;<br />
* Operation and control on alternating plasma current regimes; <br />
* Testing of liquid metal limiter concept; <br />
* Development and upgrade of diagnostics; <br />
* Test bed facility for new data acquisition concepts and hardware.<br />
===Theory contribution===<br />
Understanding turbulent transport is important to optimize the plasma confinement and for predicting the performance of future devices. Research on the comprehensive investigation of the multi-scale physics aspects of the edge turbulence, from its origin to the impact on transport including plasma-wall interaction. ISTTOK is ideal for edge physics studies due to its flexibility, low operation costs, short time scale for diagnostics implementation and compatibility with electrostatic probes. The universality of several edge physics phenomena was verified in different devices, confirming the relevance of these studies in small devices. Present activities include: <br />
*Contribute to a better understanding of spontaneously generated large-scale sheared flows and its role in regulating plasma transport.<br />
*Characterize and control the SOL intermittent transport.<br />
*Develop different electrical probes systems for edge studies.<br />
*Provide synergies between theory and experimental groups working on edge/SOL physics.<br />
*Develop analysis tools required to process the massive experimental data obtained . <br />
<br />
===Diagnostics development===<br />
<br />
Further studies on the ISTTOK plasma emissivity reconstruction using analytical methods, aiming at the best choice for real-time implementation in ISTTOK.<br />
Upgrade existing tomographic cameras to 3 x 16 channels in order to improve spatial resolution for enhanced emissivity reconstruction.<br />
Developing and building a retarding electrostatic field cylindrical energy analyzer (CEA) to measure plasma potentials in the core and their fluctuations. <br />
===Main experimental achievements===<br />
====AC operation====<br />
Due to iron core saturation, operation of ISTTOK in single pulse mode is limited to 35 ms plasma duration. ISTTOK has suffer a major update of its control systems and power supplies to operate in AC mode increasing that parameter to more than 1000 ms. Within this line of research present activities include:<br />
*Operation of the tokamak ISTTOK in a multi-cycle alternating plasma current regime, to obtain long duration discharges.<br />
*Implementation of a real-time plasma control system and study of the control of long duration AC discharges in ISTTOK.<br />
*Development of advanced gas feed control to improve reproducible and reliable plasmas with high performance.<br />
Testing of liquid metal PFC<br />
<br />
====Liquid metals as PFCs====<br />
One of the most challenging issues with regards to the operation of a future fusion reactor is related to plasma-wall interaction. Solid materials exposed to fusion plasmas are known to suffer significant damage that reduces wall lifetime. Liquid metals have proven to be of relevance for PFC protection. Due to ISTTOK characteristics its programme has also focused on testing liquid metals PFC´s and their properties:<br />
*Develop a novel Liquid Metal Limiter based on micro-channels structures.<br />
*Build and test the new LML concept using gallium as liquid metal.<br />
*Expose this PFC to ISTTOK plasmas.<br />
*Study the behavior of the limiter surface temperature increase with liquid metal re-circulation.<br />
<br />
<br />
===Data acquisition and control===<br />
Implementation of a control system based on an optimized state-space model for real time control of the plasma current magnitude and centroid position retrieved by a twelve mirnov coils poloidal set.<br />
<br />
==Physical parameters==<br />
==Nominal plasma parameters==<br />
==Precedents==<br />
===TORTUR I===<br />
Tortur was a tokamak designed in Grenoble with an initial primary to secondary winding ratio of 1:1, as the stabilizing cooper-shell was used as well as the primary. A very high current had to be feed in this primary and short discharges were obtained (up to 8 ms). The stainless steel 625 vessel was divided in two C-sections and equiped with 33 ports of 35mm, constructed by Avica Equipment, England. Basically the vessel is port structures welded together by a thin bellow of 0.15mm with an inner diameter of 200mm<br />
<br />
===TORTUR II===<br />
Tortur II undergo a vessel upgrade of the former one by the same manufacturer, assuming the actual form os ISTTOK. Besides that was equipped with a iron-core transformer with 20:1 or 40:1 transformer relation.<br />
<br />
===ISTTOK@XX===<br />
After the commissioning in Portugal, Tortur became the IST TOKamak, ISTTOK. During XX century is was operated with two capacitors banks as it's predecessor and only with forward current. The main systems have been updated, namely the vacuum systems, the plant control systems and data acquisition.<br />
Discharges were started based on a cold plasma generated by the TORTUR RF generator but due to the high noise have been soon replaced by an electron beam source (80 eV, tungsten filament) situated on the high field side close to the SOL. The hot plasma was started by the high voltage bank (1-5kV, 100uF, 2-3ms) and then an electrolytic bank (0.8F, 350V, 40-50ms) took over.<br />
<br />
==Main components==<br />
<br />
<br />
== Onde começar ==<br />
<br />
* [[ISTTOK]]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Manual:FAQ Perguntas e respostas frequentes sobre o MediaWiki]<br />
* [https://lists.wikimedia.org/mailman/listinfo/mediawiki-announce Subscreva a lista de divulgação de novas versões do MediaWiki]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Localisation#Translation_resources Regionalize o MediaWiki para a sua língua]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Manual:Combating_spam Aprenda a combater <i>spam</i> na sua wiki]</div>Isttok-adminhttps://isttok.tecnico.ulisboa.pt/~isttok.daemon/index.php?title=ISTTOK_-_Wiki&diff=30ISTTOK - Wiki2018-04-20T14:34:49Z<p>Isttok-admin: </p>
<hr />
<div><strong>IST Tokamak - ISTTOK</strong><br />
<br />
=Description=<br />
<br />
The ISTTOK Tokamak ("Instituto Superior Técnico TOKamak") is a research fusion reactor (tokamak) of the Instituto Superior Técnico.<br />
<br />
The ISTTOK Tokamak ("Instituto Superior Tecnico TOKamak") is a research fusion reactor (tokamak) of the Instituto Superior Tecnico. It has a circular cross-section due to a poloidal graphite limiter and an iron core transformer. This magnetic confinement experiment has been built from some components (supporting structure, vacuum chamber, copper shell, transformer, toroidal magnetic field coils, radio-frequency generator, and capacitor banks) of the ex-tokamak TORTUR which was de-commissioned by the Association EURATOM/FOM in 1988.<br />
<br />
[[File:Isttok.jpg]]<br />
==Goals and research objectives==<br />
The scientific programme has been based on: <br />
* Edge plasma turbulence studies;<br />
* Operation and control on alternating plasma current regimes; <br />
* Testing of liquid metal limiter concept; <br />
* Development and upgrade of diagnostics; <br />
* Test bed facility for new data acquisition concepts and hardware.<br />
===Theory contribution===<br />
Understanding turbulent transport is important to optimize the plasma confinement and for predicting the performance of future devices. Research on the comprehensive investigation of the multi-scale physics aspects of the edge turbulence, from its origin to the impact on transport including plasma-wall interaction. ISTTOK is ideal for edge physics studies due to its flexibility, low operation costs, short time scale for diagnostics implementation and compatibility with electrostatic probes. The universality of several edge physics phenomena was verified in different devices, confirming the relevance of these studies in small devices. Present activities include: <br />
*Contribute to a better understanding of spontaneously generated large-scale sheared flows and its role in regulating plasma transport.<br />
*Characterize and control the SOL intermittent transport.<br />
*Develop different electrical probes systems for edge studies.<br />
*Provide synergies between theory and experimental groups working on edge/SOL physics.<br />
*Develop analysis tools required to process the massive experimental data obtained . <br />
<br />
===Diagnostics development===<br />
<br />
Further studies on the ISTTOK plasma emissivity reconstruction using analytical methods, aiming at the best choice for real-time implementation in ISTTOK.<br />
Upgrade existing tomographic cameras to 3 x 16 channels in order to improve spatial resolution for enhanced emissivity reconstruction.<br />
Developing and building a retarding electrostatic field cylindrical energy analyzer (CEA) to measure plasma potentials in the core and their fluctuations. <br />
===Main experimental achievements===<br />
====AC operation====<br />
Due to iron core saturation, operation of ISTTOK in single pulse mode is limited to 35 ms plasma duration. ISTTOK has suffer a major update of its control systems and power supplies to operate in AC mode increasing that parameter to more than 1000 ms. Within this line of research present activities include:<br />
*Operation of the tokamak ISTTOK in a multi-cycle alternating plasma current regime, to obtain long duration discharges.<br />
*Implementation of a real-time plasma control system and study of the control of long duration AC discharges in ISTTOK.<br />
*Development of advanced gas feed control to improve reproducible and reliable plasmas with high performance.<br />
Testing of liquid metal PFC<br />
<br />
====Liquid metals as PFCs====<br />
One of the most challenging issues with regards to the operation of a future fusion reactor is related to plasma-wall interaction. Solid materials exposed to fusion plasmas are known to suffer significant damage that reduces wall lifetime. Liquid metals have proven to be of relevance for PFC protection. Due to ISTTOK characteristics its programme has also focused on testing liquid metals PFC´s and their properties:<br />
*Develop a novel Liquid Metal Limiter based on micro-channels structures.<br />
*Build and test the new LML concept using gallium as liquid metal.<br />
*Expose this PFC to ISTTOK plasmas.<br />
*Study the behavior of the limiter surface temperature increase with liquid metal re-circulation.<br />
<br />
<br />
===Data acquisition and control===<br />
Implementation of a control system based on an optimized state-space model for real time control of the plasma current magnitude and centroid position retrieved by a twelve mirnov coils poloidal set.<br />
<br />
==Physical parameters==<br />
==Nominal plasma parameters==<br />
==Precedents==<br />
===TORTUR I===<br />
===TORTUR II===<br />
<br />
==Main components==<br />
<br />
<br />
== Onde começar ==<br />
<br />
* [[ISTTOK]]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Manual:FAQ Perguntas e respostas frequentes sobre o MediaWiki]<br />
* [https://lists.wikimedia.org/mailman/listinfo/mediawiki-announce Subscreva a lista de divulgação de novas versões do MediaWiki]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Localisation#Translation_resources Regionalize o MediaWiki para a sua língua]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Manual:Combating_spam Aprenda a combater <i>spam</i> na sua wiki]</div>Isttok-adminhttps://isttok.tecnico.ulisboa.pt/~isttok.daemon/index.php?title=ISTTOK&diff=28ISTTOK2018-04-13T16:01:04Z<p>Isttok-admin: </p>
<hr />
<div><br />
The '''''ISTTOK Tokamak''''' ("Instituto Superior Técnico TOKamak") is a research [[nuclear fusion|fusion]] reactor ([[tokamak]]) of the [[Instituto Superior Técnico]]. It has a circular cross-section due to a poloidal graphite limiter and an iron core transformer. Its particularity is that it is one of the few tokamaks operating in AC (alternating plasma current) regime, as well in DC regime. In 2013, the AC operation allowed the standard discharges to extend from 35 ms to more than 1s.<br />
<br />
== Characteristics ==<br />
* Minor radius: 0.085 metre<br />
* Major radius: 0.46 metre<br />
* Plasma current: ~7kA kiloAmperes<br />
* Plasma life span: 30/1000 milliseconds (DC/AC)<br />
* Maximum toroidal magnetic field: 2.8 Tesla<br />
* Nominal toroidal magnetic field: 0.3-0.6 Tesla<br />
<br />
== See also ==<br />
* [[Small Tight Aspect Ratio Tokamak]]<br />
* [[Ball-pen probe]]<br />
<br />
== External links ==<br />
* [http://www.ipfn.ist.utl.pt/portal/index.html?ctrl:cmd=render&ctrl:mode=view&ctrl:window=euratom_ist.research.magnetic.ContentsWindow&pagina.nome=euratom-ISTTOK ISTTOK official site]<br />
<br />
{{energy-stub}}<br />
{{fusion experiments}}<br />
<br />
{{DEFAULTSORT:ISTTOK Tokamak}}<br />
[[Category:Nuclear fusion]]<br />
[[Category:Nuclear research institutes]]<br />
[[Category:Fusion power]]<br />
[[Category:Research projects]]<br />
[[Category:Tokamaks]]</div>Isttok-adminhttps://isttok.tecnico.ulisboa.pt/~isttok.daemon/index.php?title=ISTTOK&diff=26ISTTOK2018-04-13T16:00:54Z<p>Isttok-admin: </p>
<hr />
<div><br />
The '''''ISTTOK Tokamak''''' ("Instituto Superior Técnico TOKamak") is a research [[nuclear fusion|fusion]] reactor ([[tokamak]]) of the [[Instituto Superior Técnico]]. It has a circular cross-section due to a poloidal graphite limiter and an iron core transformer. Its particularity is that it is one of the few tokamaks operating in AC (alternating plasma current) regime, as well in DC regime. In 2013, the AC operation allowed the standard discharges to extend from 35 ms to more than 1s.<br />
<br />
== Characteristics ==<br />
* Minor radius: 0.085 metres<br />
* Major radius: 0.46 metre<br />
* Plasma current: ~7kA kiloAmperes<br />
* Plasma life span: 30/1000 milliseconds (DC/AC)<br />
* Maximum toroidal magnetic field: 2.8 Tesla<br />
* Nominal toroidal magnetic field: 0.3-0.6 Tesla<br />
<br />
== See also ==<br />
* [[Small Tight Aspect Ratio Tokamak]]<br />
* [[Ball-pen probe]]<br />
<br />
== External links ==<br />
* [http://www.ipfn.ist.utl.pt/portal/index.html?ctrl:cmd=render&ctrl:mode=view&ctrl:window=euratom_ist.research.magnetic.ContentsWindow&pagina.nome=euratom-ISTTOK ISTTOK official site]<br />
<br />
{{energy-stub}}<br />
{{fusion experiments}}<br />
<br />
{{DEFAULTSORT:ISTTOK Tokamak}}<br />
[[Category:Nuclear fusion]]<br />
[[Category:Nuclear research institutes]]<br />
[[Category:Fusion power]]<br />
[[Category:Research projects]]<br />
[[Category:Tokamaks]]</div>Isttok-adminhttps://isttok.tecnico.ulisboa.pt/~isttok.daemon/index.php?title=ISTTOK_-_Wiki&diff=24ISTTOK - Wiki2018-04-11T22:48:54Z<p>Isttok-admin: </p>
<hr />
<div><strong>IST Tokamak - ISTTOK</strong><br />
<br />
The ISTTOK Tokamak ("Instituto Superior Técnico TOKamak") is a research fusion reactor (tokamak) of the Instituto Superior Técnico.<br />
<br />
[[File:Isttok.jpg]]<br />
<br />
== Onde começar ==<br />
<br />
* [[ISTTOK]]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Manual:FAQ Perguntas e respostas frequentes sobre o MediaWiki]<br />
* [https://lists.wikimedia.org/mailman/listinfo/mediawiki-announce Subscreva a lista de divulgação de novas versões do MediaWiki]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Localisation#Translation_resources Regionalize o MediaWiki para a sua língua]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Manual:Combating_spam Aprenda a combater <i>spam</i> na sua wiki]</div>Isttok-adminhttps://isttok.tecnico.ulisboa.pt/~isttok.daemon/index.php?title=Ficheiro:Isttok.jpg&diff=22Ficheiro:Isttok.jpg2018-04-11T22:47:55Z<p>Isttok-admin: Foto do ISTTOK</p>
<hr />
<div>Foto do ISTTOK</div>Isttok-adminhttps://isttok.tecnico.ulisboa.pt/~isttok.daemon/index.php?title=ISTTOK_-_Wiki&diff=20ISTTOK - Wiki2018-04-11T16:51:21Z<p>Isttok-admin: </p>
<hr />
<div><strong>IST Tokamak - ISTTOK</strong><br />
<br />
The ISTTOK Tokamak ("Instituto Superior Técnico TOKamak") is a research fusion reactor (tokamak) of the Instituto Superior Técnico.<br />
<br />
== Onde começar ==<br />
<br />
* [[ISTTOK]]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Manual:FAQ Perguntas e respostas frequentes sobre o MediaWiki]<br />
* [https://lists.wikimedia.org/mailman/listinfo/mediawiki-announce Subscreva a lista de divulgação de novas versões do MediaWiki]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Localisation#Translation_resources Regionalize o MediaWiki para a sua língua]<br />
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<div><strong>IST Tokamak - ISTTOK</strong><br />
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The ISTTOK Tokamak ("Instituto Superior Técnico TOKamak") is a research fusion reactor (tokamak) of the Instituto Superior Técnico.<br />
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== Onde começar ==<br />
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* [ISTTOK]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Manual:FAQ Perguntas e respostas frequentes sobre o MediaWiki]<br />
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<div><br />
The '''''ISTTOK Tokamak''''' ("Instituto Superior Técnico TOKamak") is a research [[nuclear fusion|fusion]] reactor ([[tokamak]]) of the [[Instituto Superior Técnico]]. It has a circular cross-section due to a poloidal graphite limiter and an iron core transformer. Its particularity is that it is one of the few tokamaks operating in AC (alternating plasma current) regime, as well in DC regime. In 2013, the AC operation allowed the standard discharges to extend from 35 ms to more than 1s.<br />
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== Characteristics ==<br />
* Minor radius: 0.085 metre<br />
* Major radius: 0.46 metre<br />
* Plasma current: ~7kA kiloAmperes<br />
* Plasma life span: 30/1000 milliseconds (DC/AC)<br />
* Maximum toroidal magnetic field: 2.8 Tesla<br />
* Nominal toroidal magnetic field: 0.3-0.6 Tesla<br />
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== See also ==<br />
* [[Small Tight Aspect Ratio Tokamak]]<br />
* [[Ball-pen probe]]<br />
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== External links ==<br />
* [http://www.ipfn.ist.utl.pt/portal/index.html?ctrl:cmd=render&ctrl:mode=view&ctrl:window=euratom_ist.research.magnetic.ContentsWindow&pagina.nome=euratom-ISTTOK ISTTOK official site]<br />
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{{energy-stub}}<br />
{{fusion experiments}}<br />
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{{DEFAULTSORT:ISTTOK Tokamak}}<br />
[[Category:Nuclear fusion]]<br />
[[Category:Nuclear research institutes]]<br />
[[Category:Fusion power]]<br />
[[Category:Research projects]]<br />
[[Category:Tokamaks]]</div>Isttok-adminhttps://isttok.tecnico.ulisboa.pt/~isttok.daemon/index.php?title=ISTTOK_-_Wiki&diff=14ISTTOK - Wiki2018-04-11T16:49:16Z<p>Isttok-admin: </p>
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<div><strong>IST Tokamak - ISTTOK</strong><br />
<br />
The ISTTOK Tokamak ("Instituto Superior Técnico TOKamak") is a research fusion reactor (tokamak) of the Instituto Superior Técnico.<br />
<br />
== Onde começar ==<br />
<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Manual:Configuration_settings Lista de opções de configuração]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Manual:FAQ Perguntas e respostas frequentes sobre o MediaWiki]<br />
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* [https://www.mediawiki.org/wiki/Special:MyLanguage/Manual:Combating_spam Aprenda a combater <i>spam</i> na sua wiki]</div>Isttok-adminhttps://isttok.tecnico.ulisboa.pt/~isttok.daemon/index.php?title=ISTTOK_-_Wiki&diff=12ISTTOK - Wiki2018-04-11T16:49:06Z<p>Isttok-admin: </p>
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<div><strong>IST Tokamak - ISTTOK</strong>7<br />
<br />
The ISTTOK Tokamak ("Instituto Superior Técnico TOKamak") is a research fusion reactor (tokamak) of the Instituto Superior Técnico.<br />
<br />
== Onde começar ==<br />
<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Manual:Configuration_settings Lista de opções de configuração]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Manual:FAQ Perguntas e respostas frequentes sobre o MediaWiki]<br />
* [https://lists.wikimedia.org/mailman/listinfo/mediawiki-announce Subscreva a lista de divulgação de novas versões do MediaWiki]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Localisation#Translation_resources Regionalize o MediaWiki para a sua língua]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Manual:Combating_spam Aprenda a combater <i>spam</i> na sua wiki]</div>Isttok-adminhttps://isttok.tecnico.ulisboa.pt/~isttok.daemon/index.php?title=ISTTOK_-_Wiki&diff=10ISTTOK - Wiki2018-04-11T16:48:16Z<p>Isttok-admin: Isttok-admin moveu ISTTOK - Wiki1 para ISTTOK - Wiki sem deixar um redirecionamento</p>
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== Onde começar ==<br />
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* [https://www.mediawiki.org/wiki/Special:MyLanguage/Manual:Configuration_settings Lista de opções de configuração]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Manual:FAQ Perguntas e respostas frequentes sobre o MediaWiki]<br />
* [https://lists.wikimedia.org/mailman/listinfo/mediawiki-announce Subscreva a lista de divulgação de novas versões do MediaWiki]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Localisation#Translation_resources Regionalize o MediaWiki para a sua língua]<br />
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<div><strong>O MediaWiki foi instalado.</strong><br />
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Consulte a [https://www.mediawiki.org/wiki/Special:MyLanguage/Help:Contents Ajuda do MediaWiki] para informações sobre o uso do software wiki.<br />
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== Onde começar ==<br />
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* [https://www.mediawiki.org/wiki/Special:MyLanguage/Manual:Configuration_settings Lista de opções de configuração]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Manual:FAQ Perguntas e respostas frequentes sobre o MediaWiki]<br />
* [https://lists.wikimedia.org/mailman/listinfo/mediawiki-announce Subscreva a lista de divulgação de novas versões do MediaWiki]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Localisation#Translation_resources Regionalize o MediaWiki para a sua língua]<br />
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<div><strong>O MediaWiki foi instalado.</strong><br />
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Consulte a [https://www.mediawiki.org/wiki/Special:MyLanguage/Help:Contents Ajuda do MediaWiki] para informações sobre o uso do software wiki.<br />
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== Onde começar ==<br />
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* [https://www.mediawiki.org/wiki/Special:MyLanguage/Manual:Configuration_settings Lista de opções de configuração]<br />
* [https://www.mediawiki.org/wiki/Special:MyLanguage/Manual:FAQ Perguntas e respostas frequentes sobre o MediaWiki]<br />
* [https://lists.wikimedia.org/mailman/listinfo/mediawiki-announce Subscreva a lista de divulgação de novas versões do MediaWiki]<br />
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<div>#REDIRECIONAMENTO [[ISTTOK - Wiki]]</div>Isttok-admin