FusionWiki - User contributions [en]

LNF:Organization

2023-02-02T12:02:58Z

Acappa:

== Laboratorio Nacional de Fusión ==

Asociación [[Euratom]]-[[CIEMAT]]: see [[Laboratorio Nacional de Fusión]].

Contact information is also available via the [http://www.ciemat.es/cargarFichaOrganizacion.do?idOrganizacion=F00 CIEMAT website]

The telephone numbers listed below are extensions; to call from outside the laboratory, dial: +34-91346xxxx, where xxxx is the extension. (When using 4-digit dialing from inside the laboratory: substitute any initial "0" by a "7".)

[https://www.gruptelecom.com/wp-content/uploads/2018/07/Manual_Unify_CP-200.pdf IP-phone manual]

{|class="wikitable" style="vertical-align:top;"||
|-
!Name!!Telephone (old)!!IP-phone
|-
| Hidalgo Vera, Carlos, Director || 6498 ||
|-
| Guerard Ortego, Carlos Kjell || - ||
|-
|}

=== TJ-II Experimental Division ===

{|class="wikitable" style="vertical-align:top;"||
|-
!Name!!Telephone (old)!!IP-phone
|-
| Alonso de Pablo, Arturo || +49 3834 88 2342 ||
|-
| Baciero Adrados, Alfonso || 6493 || 362601
|-
| Blanco Villareal, Emilio J. || 7904 ||
|-
| de la Cal Heusch, Eduardo || 6317 ||
|-
| Carralero Ortiz, Daniel || 7852 ||
|-
| Castro Rojo, Rodrigo || 6419 ||
|-
| Estrada García, Mª. Teresa || 0845 ||
|-
| Fontdecaba Climent, Jose María || 6642 ||
|-
| García Cortés, Mª. Isabel || 6515 || 362625
|-
| Hernanz Hernanz, Francisco J. || 6641 ||
|-
| López Miranda, Belén || || 362093
|-
| McCarthy, Kieran Joseph || 0846 || 362934
|-
| Medina Yela, Francisco || 0847 || 362935
|-
| Ochando Garcia, Mª. Antonia || 6462 ||
|-
| de Pablos Hernández, Jose Luis || 6374 ||
|-
| Panadero Álvarez, Nerea || 6642 || 362781
|-
| Pastor Díaz, Ignacio || 6324 ||
|-
| Pastor Santos, Carmen || || 362564
|-
| Rattá Gutiérrez, Giuseppe A. || 7917 ||
|-
| Rodríguez Fernández, Mª. Carmen || 2611 ||
|-
| [[User:Admin|van Milligen, Boudewijn]] || 6379 || 362482
|-
| Vega Sánchez, Jesús Antonio || 6474 ||
|}

=== TJ-II Operation Division===

{|class="wikitable" style="vertical-align:top;"||
|-
!Name!!Telephone (old)!!IP-phone
|-
| Ascasíbar, Enrique, Head Investigator || 6369 ||
|-
| Alegre Castro, Daniel || 0914 ||
|-
| Cappa Ascasíbar, Alvaro || 6646 Sala de Control ECRH 6828 || 362784
|-
| Cebrián Ruiz, Luis A. || 6338 ||
|-
| Chamorro Lastra, Manuel || 6641 ||
|-
| García Gomez, Raúl || 6641 ||
|-
| Guasp Pérez, Jose || 6510 ||
|-
| Guisse Arévalo, Víctor H. || 6285 ||
|-
| Liniers Vazquez, Macarena || 0844 Sala de Control NBI 6851 ||
|-
| Martín Diaz, Fernando || 0920 Sala de Control NBI 6851 ||
|-
| Martinez Fernandez, Jose || 6646 Sala de Control ECRH 6828 || 362785
|-
| Bueno Jañez, Luis Alberto || 6285 ||
|-
| Miguel Honrubia, Francisco J. || 6762 ||
|-
| Navarro Santana Miguel || 6824 ||
|-
| Pereira Gonzalez, Augusto || 0929 ||
|-
| Portas Ferreiro, Ana Belén || 0929 ||
|-
| Ros Vivancos, Alfonso || 6642 Sala de Control ECRH 6828 Lab. μOndas 6808 || 362782
|-
| Sánchez Sarabia, Emilio || 6762 ||
|-
| Sebastián Alfaro, José Antonio || 6684 Sala de Control NBI 6851 || 362828
|-
| Tabarés Vazquez, Francisco Luis || 6458 ||
|-
| Tafalla García, David || 0843 ||
|-
| Tolkachev, Alexander || 6828 ||
|}

=== Fusion Theory Unit ===

{|class="wikitable" style="vertical-align:top;"||
|-
!Name!!Telephone (old)!!IP-phone
|-
| Calvo Rubio, Iván, Head Investigator || 6739 || 362872
|-
| Escoto López, Francisco Javier || ||
|-
| García Regaña, José Manuel || 7850 || 362938
|-
| Godino Sedano, Guillermo Luis || 7920 || 362780
|-
| González Jerez, Antonio || 7916 || 363000
|-
| López Bruna, Daniel || 6638 ||
|-
| [[User:Esolano|Solano (Rodríguez-Solano Ribeiro), Emilia R.]]|| 6153 ||
|-
| Sánchez González, Edilberto || 6162 || 362264
|-
| Thienpondt, Hanne || 2538 || 362037
|-
| Velasco Garasa, José Luis || 6504 || 362610
|}

=== Engineering Unit ===

{|class="wikitable" style="vertical-align:top;"||
|-
!Name!!Telephone (old)!!IP-phone
|-
| Alonso, José Javier, Head Investigator || 6639 ||
|-
| Cabrera Pérez, Santiago || || 362994
|-
| Carrasco García, Ricardo || 7928 ||
|-
| Fernández Navarro, Alejandro || 6637 || 362771
|-
| Jimenez Denche, Andrés Enrique || 6584 ||
|-
| Kirpitchev, Igor || 6337 ||
|-
| Lapayese Puebla, Fernando || 0928 ||
|-
| Medrano Casanova, Mercedes || 6639 ||
|-
| Méndez Montero, Purificación || 6337 ||
|-
| de la Peña Gómez, Ángel || 6644 ||
|-
| Queral Mas, Vicente || 6419 || 362518
|-
| Ramos Rivero, Francisco || 6584 ||
|-
| Rincón Rincón, María Esther || 6637 ||
|-
| Soleto Palomo, M. Alfonso || 6636 ||
|-
| Weber Suárez, Moisés || 6636 ||
|}

=== Technology Division ===

{|class="wikitable" style="vertical-align:top;"||
|-
!Name!!Telephone (old)!!IP-phone
|-
| Rapisarda Socorro, David, Head Investigator || 0913/6335 (prov) || 362998
|-
| Brañas Lasala, Beatriz || 6289 ||
|-
| Carella, Elisabetta || 6507 ||
|-
| Fernández Berceruelo, Iván || 2579 ||
|-
| García Gonzalez, Juan Manuel || 7842 ||
|-
| Garcinuño Pindado, Belit || 6584 || 362717
|-
| Gonzalez Viada, María || 2582 || 362073
|-
| Gutierrez Pérez, Víctor || 6307 || 362413
|-
| Hernandez Diaz, Mª. Teresa || 2581 ||
|-
| Herranz Marco, Jesús Antonio || 0848 ||
|-
| Jimenez Baena, Francisco M. || 6204 ||
|-
| Jiménez Rey, David || 6640 ||
|-
| Malo Huerta, Marta || 6636 || 362769
|-
| Martín Laso, Montserrat || 6512 ||
|-
| Molla Lorente, Joaquín || 6580 ||
|-
| de la Morena Álvarez-Palencia, Cristina || 2600 ||
|-
| Moroño Guadalajara, Alejandro A. || 6372 ||
|-
| Mota García, Fernando || 6578 || 362708
|-
| Navas, Julia || || 362428
|-
| Ortíz, Christophe || 2582 || 362074
|-
| Ortiz Gandía, Maribel || 2582 || 362075
|-
| Palermo, Iole || 6784 ||
|-
| Patiño, Julian || || 362428
|-
| Regidor Serrano, David || 6584 ||
|-
| Roldán Blanco, Marcelo || 2574 Lab. 6512 ||
|-
| Román Chacón, Raquel || 6203 ||
|-
| Sánchez Sanz, Fernando José || 6578 FIB-SEM 6790 ||
|-
| Valle Paisan, Francisco J. || 6204 ||
|-
| Vila Vazquez, Rafael Alberto || 6580 ||
|-
| Villamayor Callejo, Víctor || 6578 ||
|-
|}

=== Support Unit ===

{|class="wikitable" style="vertical-align:top;"||
|-
!Name!!Telephone (old)!!IP-phone
|-
| Barrera Orte, Laura || || 362262
|-
| Fernandez-Mayoralas López, Lorena || 6663 ||
|-
| Moreno García, Sabina || 6159 ||
|-
| Sánchez Rubio, Cristina || 6738 ||
|}

TJ-II: Determination of the spatial periodicity of NBI-driven Alfvén Eigenmodes and study of its magnetic configuration dependence

2022-01-26T08:45:12Z

Acappa: /* Description of required resources */

== Experimental campaign ==
Spring 2022

== Proposal title ==
Determination of the spatial periodicity of NBI-driven Alfvén Eigenmodes and study of its magnetic configuration dependence.

== Name and affiliation of proponent ==
[https://orcid.org/0000-0002-2250-9209 Álvaro Cappa], CIEMAT.
[https://orcid.org/0000-0000-0000-0000 Pedro Pons], CIEMAT.
[https://orcid.org/0000-0003-2101-0112 Macarena Liniers], CIEMAT.
[https://orcid.org/0000-0002-2250-9209 Enrique Ascasíbar], CIEMAT.

== Details of contact person at LNF ==
[https://orcid.org/0000-0002-2250-9209 Enrique Ascasíbar], CIEMAT.

== Description of the activity ==

MHD activity produced by Alfvén Eigenmodes (AEs) is routinely observed in NBI-heated TJ-II plasmas <ref>A. Cappa et al, Nuclear Fusion, 61(6):066019 (2021), and references therein</ref>. The results provided by recently installed sets of helical magnetic coils complement the previous experimental data and, together with advanced analysis tools like the 3D Lomb periodogram <ref>S. Zegenhagen, et al., Plasma Physics and Controlled Fusion, 48(9):1333–1346 (2006)</ref> allows the determination of the AEs spatial periodicity with an accuracy non reachable so far.

With this goal in mind we propose to study the alfvénic activity produced by both co and counter NBI injectors separately, as well as the one produced by simultaneous, balanced heating with both injectors (compensated plasma current). We plan to perform this study in at least two magnetic configurations, 100_44_64 (edge_iota 1.65) and 100_60_68 (1.77), looking for the expected influence of the configuration on the shear Alfvén spectrum. It time allows we do not discard the possibility of scanning the injector parameters (energy, beam current) to study their influence on the observed AEs.

Since we will be looking for reasonably stationary plasma density conditions to facilitate the mode analysis, we do not discard the use of moderate ECH heating during the NBI plasma phase.

== International or National funding project or entity ==

International: EUROfusion Consortium under grant agreements 633053 (FP8) and 101052200 (FP9).

National: Spanish Ministry of Science and Innovation under grants FIS2017-88892-P and FIS2017-85252-R

== Description of required resources ==
Required resources:
* Two days of good NBI plasma operation (aprox. 35 discharges each) with reasonably good plasma density control.
* Essential diagnostic systems: Mirnov coils (helical and poloidal arrays) and CNPA measurements are mandatory. Besides the common shot to shot diagnostics (ECE, Thomson, Interferometry, Radiation), all systems providing edge plasma profiles are needed. If possible, Doppler Reflectometer, HIBP. MSE would also be desirable to evaluate configuration changes induced by non-totally balanced currents. FILD is also desirable to monitor fast ion losses and relate the level of losses to the Alfven activity.
* Type of plasmas (heating configuration): NBI (both injectors) and ECH.
* Specific requirements on wall conditioning if any: Good plasma density control usually means that the operation days must be allocated close after the boron/lihium conditioning of the vacuum vessel.
* External users: need a local computer account for data access: No
* Any external equipment to be integrated? No

== Preferred dates and degree of flexibility ==
Preferred dates:

If possible, one day in February and another in March



== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II:Searching for AEs suppression scenarios using off-axis ECCD

2022-01-26T08:30:41Z

Acappa: /* Description of required resources */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Searching for AEs suppression scenarios using off-axis ECCD'''

== Name and affiliation of proponent ==
Á. Cappa, J. Martínez, E. Ascasíbar, K.J. McCarthy, P. Pons, T. Estrada, D. Zarzoso, C. Hidalgo

== Details of contact person at LNF ==
If applicable, enter contact person here or write N/A

== Description of the activity ==
The goal of the proposal is to find ECRH launching configurations for which the amplitude of
NBI-driven Alfvén Eigenmodes (AEs) is mitigated. Besides the interest that such scenarios have for the fast particles topic, studies of coupling between NBI-driven AEs and low frequency zonal flows may also benefit from them.
Many scenarios making use of different "control" parameters
have already been tested in past experimental sessions, showing always strong changes in AEs activity.
Plasma density variations and changes of the rotational transform profile due to the
many contributions to the total plasma current (NBCD, ECCD, Bootstrap current) are the parameters
with the higher impact. However, although inducing modifications in the general spectrum of the excited modes,
none of the investigated scenarios show a clear possibility to suppress AEs without inducing large
changes in plasma parameters, being the most promising the one employing ECCD.
In this particular case we intend to investigate the effect of
off-axis ECCD at different plasma radius.

== Experimental plan ==

[[File:imagen1.png |thumb|right|300px| Figure 1. Heating scheme. ECH1 beam, used to induce current, is
launched with two different power levels for gyrotron stability purposes]]

Until now, only ECCD on-axis has been investigated. We will now try to modify the rotational transform profile by inducing ECCD off-axis with
different levels of power at different plasma radius. '''The success of the proposal depends on whether or not the gyrotron that will be used to drive the current (ECH1) can be operated as shown in figure 1'''. To this end, previous tube conditionning sessions will be needed to ensure that the gyrotron can work with different levels of anode voltage in the same shot and thus deliver different levels of power. The heating power set-up shown in figure 1 will allow us to investigate the effect of ECCD using different combinations of ECH1 beam power and ECCD efficiency.
With this set-up, ECH2 power (always with <math>n_{||}=0</math>) is used for start-up and density control in the NBI phase. Ideally, there should be no power in the first gyrotron until the central part of the NBI phase, in which the reference shot with <math>n_{||}=0</math> in ECH1 will be compared to the shots obtained by changing the injection direction of ECH1. For stability purposes of the gyrotron, and depending on the result of the conditionning tests, a small amount of power may be required from the begginning of the shot until higher power is requested.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==
Required resources:
* Number of plasma discharges or days of operation: One day - 20 useful shots
* Essential diagnostic systems: Besides the common shot to shot diagnostics (ECE, Thomson, Interferometry, Radiation), all systems providing edge plasma profiles are needed. Moreover, HIBP to measure mode radial structure, Doppler Reflectometer, Mirnov coils (both helical and poloidal arrays) and CNPA measurements are mandatory. MSE would also be desirable to measure changes induced by ECCD. FILD is also desirable in order to monitor the different levels of fast ions losses in each heating configuration.
* Type of plasmas (heating configuration): ECRH + NBI-1 hydrogen plasmas following the heating scheme shown in Figure 1.
* Specific requirements on wall conditioning if any:
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: no

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II: Calibration of the helical arrays of Mirnov coils

2022-01-24T15:31:01Z

Acappa: /* Description of required resources */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Calibration of the helical arrays of Mirnov coils'''

== Name and affiliation of proponent ==
A. Cappa, E. Ascasibar, P. Pons

== Details of contact person at LNF ==
N/A

== Description of the activity ==
The calibration of the recently commissioned arrays of Mirnov coils has been performed by comparing the vacuum magnetic field of the standard configuration to the measurements of the integrated field obtained by each of the coils. Reproducibility is very good but only one magnetic configuration has been used and thus the calibration is sensitive to any error in the modelling of the theoretical field used for comparison. To ensure that this calibration, which is essential to correctly determine the mode numbers of the MHD perturbations, is correct, it is worthwhile to perform this exercise for different magnetic field distributions inside the device, either constructed by using other configurations or by preparing specific shots using the different CC, VF or HSX conductors separately. This proposal does not require the creation of plasma and can be executed at the beginning of the day previous to the plasma operation.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==
Required resources:
* Number of plasma discharges or days of operation: 5 shots with different field distributions
* Essential diagnostic systems: Mirnov Coils
* Type of plasmas (heating configuration): NO PLASMAS ARE REQUIRED
* Specific requirements on wall conditioning if any: NO
* External users: need a local computer account for data access: NO
* Any external equipment to be integrated? Provide description and integration needs:NO

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II: Calibration of the helical arrays of Mirnov coils

2022-01-24T15:16:24Z

Acappa: /* Description of the activity */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Calibration of the helical arrays of Mirnov coils'''

== Name and affiliation of proponent ==
A. Cappa, E. Ascasibar, P. Pons

== Details of contact person at LNF ==
N/A

== Description of the activity ==
The calibration of the recently commissioned arrays of Mirnov coils has been performed by comparing the vacuum magnetic field of the standard configuration to the measurements of the integrated field obtained by each of the coils. Reproducibility is very good but only one magnetic configuration has been used and thus the calibration is sensitive to any error in the modelling of the theoretical field used for comparison. To ensure that this calibration, which is essential to correctly determine the mode numbers of the MHD perturbations, is correct, it is worthwhile to perform this exercise for different magnetic field distributions inside the device, either constructed by using other configurations or by preparing specific shots using the different CC, VF or HSX conductors separately. This proposal does not require the creation of plasma and can be executed at the beginning of the day previous to the plasma operation.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==
Required resources:
* Number of plasma discharges or days of operation:
* Essential diagnostic systems:
* Type of plasmas (heating configuration):
* Specific requirements on wall conditioning if any:
* External users: need a local computer account for data access: yes/no
* Any external equipment to be integrated? Provide description and integration needs:

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II: Calibration of the helical arrays of Mirnov coils

2022-01-24T15:01:33Z

Acappa: /* Details of contact person at LNF */

TJ-II: Calibration of the helical arrays of Mirnov coils

2022-01-24T15:01:24Z

Acappa: /* Name and affiliation of proponent */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Calibration of the helical arrays of Mirnov coils'''

== Name and affiliation of proponent ==
A. Cappa, E. Ascasibar, P. Pons

== Details of contact person at LNF ==
If applicable, enter contact person here or write N/A

== Description of the activity ==
Enter description here <ref>A. Einstein, Journal of Exceptional Results (2017)</ref>, including motivation/objectives and experience of the proponent (typically one-two pages)

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==
Required resources:
* Number of plasma discharges or days of operation:
* Essential diagnostic systems:
* Type of plasmas (heating configuration):
* Specific requirements on wall conditioning if any:
* External users: need a local computer account for data access: yes/no
* Any external equipment to be integrated? Provide description and integration needs:

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II: Calibration of the helical arrays of Mirnov coils

2022-01-24T15:00:45Z

Acappa: /* Proposal title */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Calibration of the helical arrays of Mirnov coils'''

== Name and affiliation of proponent ==
Enter name, affiliation and ORCID code here

Suggested format:

[https://orcid.org/0000-0000-0000-0000 John Doe], University of Ivory Tower

== Details of contact person at LNF ==
If applicable, enter contact person here or write N/A

== Description of the activity ==
Enter description here <ref>A. Einstein, Journal of Exceptional Results (2017)</ref>, including motivation/objectives and experience of the proponent (typically one-two pages)

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==
Required resources:
* Number of plasma discharges or days of operation:
* Essential diagnostic systems:
* Type of plasmas (heating configuration):
* Specific requirements on wall conditioning if any:
* External users: need a local computer account for data access: yes/no
* Any external equipment to be integrated? Provide description and integration needs:

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II: Calibration of the helical arrays of Mirnov coils

2022-01-24T15:00:24Z

Acappa: Created page with "== Experimental campaign == Spring 2022 == Proposal title == '''Enter Title here''' == Name and affiliation of proponent == Enter name, affiliation and ORCID code here Sugg..."

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Enter Title here'''

== Name and affiliation of proponent ==
Enter name, affiliation and ORCID code here

Suggested format:

[https://orcid.org/0000-0000-0000-0000 John Doe], University of Ivory Tower

== Details of contact person at LNF ==
If applicable, enter contact person here or write N/A

== Description of the activity ==
Enter description here <ref>A. Einstein, Journal of Exceptional Results (2017)</ref>, including motivation/objectives and experience of the proponent (typically one-two pages)

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==
Required resources:
* Number of plasma discharges or days of operation:
* Essential diagnostic systems:
* Type of plasmas (heating configuration):
* Specific requirements on wall conditioning if any:
* External users: need a local computer account for data access: yes/no
* Any external equipment to be integrated? Provide description and integration needs:

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II:Searching for AEs suppression scenarios using off-axis ECCD

2022-01-21T16:27:46Z

Acappa: /* Description of required resources */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Searching for AEs suppression scenarios using off-axis ECCD'''

== Name and affiliation of proponent ==
Á. Cappa, J. Martínez, E. Ascasíbar, K.J. McCarthy, P. Pons, T. Estrada, D. Zarzoso, C. Hidalgo

== Details of contact person at LNF ==
If applicable, enter contact person here or write N/A

== Description of the activity ==
The goal of the proposal is to find ECRH launching configurations for which the amplitude of
NBI-driven Alfvén Eigenmodes (AEs) is mitigated. Besides the interest that such scenarios have for the fast particles topic, studies of coupling between NBI-driven AEs and low frequency zonal flows may also benefit from them.
Many scenarios making use of different "control" parameters
have already been tested in past experimental sessions, showing always strong changes in AEs activity.
Plasma density variations and changes of the rotational transform profile due to the
many contributions to the total plasma current (NBCD, ECCD, Bootstrap current) are the parameters
with the higher impact. However, although inducing modifications in the general spectrum of the excited modes,
none of the investigated scenarios show a clear possibility to suppress AEs without inducing large
changes in plasma parameters, being the most promising the one employing ECCD.
In this particular case we intend to investigate the effect of
off-axis ECCD at different plasma radius.

== Experimental plan ==

[[File:imagen1.png |thumb|right|300px| Figure 1. Heating scheme. ECH1 beam, used to induce current, is
launched with two different power levels for gyrotron stability purposes]]

Until now, only ECCD on-axis has been investigated. We will now try to modify the rotational transform profile by inducing ECCD off-axis with
different levels of power at different plasma radius. '''The success of the proposal depends on whether or not the gyrotron that will be used to drive the current (ECH1) can be operated as shown in figure 1'''. To this end, previous tube conditionning sessions will be needed to ensure that the gyrotron can work with different levels of anode voltage in the same shot and thus deliver different levels of power. The heating power set-up shown in figure 1 will allow us to investigate the effect of ECCD using different combinations of ECH1 beam power and ECCD efficiency.
With this set-up, ECH2 power (always with <math>n_{||}=0</math>) is used for start-up and density control in the NBI phase. Ideally, there should be no power in the first gyrotron until the central part of the NBI phase, in which the reference shot with <math>n_{||}=0</math> in ECH1 will be compared to the shots obtained by changing the injection direction of ECH1. For stability purposes of the gyrotron, and depending on the result of the conditionning tests, a small amount of power may be required from the begginning of the shot until higher power is requested.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==
Required resources:
* Number of plasma discharges or days of operation: One day - 20 useful shots
* Essential diagnostic systems: Besides the common shot to shot diagnostics (ECE, Thomson, Interferometry, Radiation), all systems providing edge plasma profiles are needed. Moreover, HIBP to measure mode radial structure, Doppler Reflectometer, Mirnov coils (both helical and poloidal arrays) and CNPA measurements are mandatory. MSE would also be desirable to measure changes induced by ECCD.
* Type of plasmas (heating configuration): ECRH + NBI-1 hydrogen plasmas following the heating scheme shown in Figure 1.
* Specific requirements on wall conditioning if any:
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: no

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II:Searching for AEs suppression scenarios using off-axis ECCD

2022-01-21T14:33:49Z

Acappa: /* Name and affiliation of proponent */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Searching for AEs suppression scenarios using off-axis ECCD'''

== Name and affiliation of proponent ==
Á. Cappa, J. Martínez, E. Ascasíbar, K.J. McCarthy, P. Pons, T. Estrada, D. Zarzoso, C. Hidalgo

== Details of contact person at LNF ==
If applicable, enter contact person here or write N/A

== Description of the activity ==
The goal of the proposal is to find ECRH launching configurations for which the amplitude of
NBI-driven Alfvén Eigenmodes (AEs) is mitigated. Besides the interest that such scenarios have for the fast particles topic, studies of coupling between NBI-driven AEs and low frequency zonal flows may also benefit from them.
Many scenarios making use of different "control" parameters
have already been tested in past experimental sessions, showing always strong changes in AEs activity.
Plasma density variations and changes of the rotational transform profile due to the
many contributions to the total plasma current (NBCD, ECCD, Bootstrap current) are the parameters
with the higher impact. However, although inducing modifications in the general spectrum of the excited modes,
none of the investigated scenarios show a clear possibility to suppress AEs without inducing large
changes in plasma parameters, being the most promising the one employing ECCD.
In this particular case we intend to investigate the effect of
off-axis ECCD at different plasma radius.

== Experimental plan ==

[[File:imagen1.png |thumb|right|300px| Figure 1. Heating scheme. ECH1 beam, used to induce current, is
launched with two different power levels for gyrotron stability purposes]]

Until now, only ECCD on-axis has been investigated. We will now try to modify the rotational transform profile by inducing ECCD off-axis with
different levels of power at different plasma radius. '''The success of the proposal depends on whether or not the gyrotron that will be used to drive the current (ECH1) can be operated as shown in figure 1'''. To this end, previous tube conditionning sessions will be needed to ensure that the gyrotron can work with different levels of anode voltage in the same shot and thus deliver different levels of power. The heating power set-up shown in figure 1 will allow us to investigate the effect of ECCD using different combinations of ECH1 beam power and ECCD efficiency.
With this set-up, ECH2 power (always with <math>n_{||}=0</math>) is used for start-up and density control in the NBI phase. Ideally, there should be no power in the first gyrotron until the central part of the NBI phase, in which the reference shot with <math>n_{||}=0</math> in ECH1 will be compared to the shots obtained by changing the injection direction of ECH1. For stability purposes of the gyrotron, and depending on the result of the conditionning tests, a small amount of power may be required from the begginning of the shot until higher power is requested.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==
Required resources:
* Number of plasma discharges or days of operation: One day - 20 useful shots
* Essential diagnostic systems: Besides the common shot to shot diagnostics (ECE, Thomson, Interferometry, Radiation), all systems providing edge plasma profiles are needed. Moreover, HIBP, Doppler Reflectometer, Mirnov coils (both helical and poloidal arrays) and CNPA meaurements are mandatory. MSE would also be desirable to measure changes induced by ECCD.
* Type of plasmas (heating configuration): ECRH + NBI-1 hydrogen plasmas following the heating scheme shown in Figure 1.
* Specific requirements on wall conditioning if any:
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: no

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II: Validation of neutral beam current drive

2022-01-21T14:31:13Z

Acappa: /* Name and affiliation of proponent */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Validation of neutral beam current drive'''

== Name and affiliation of proponent ==
A. Cappa, S. Mulas, M. Liniers, T. Estrada, E. Ascasibar, J. Velasco, K. McCarthy et al.

== Details of contact person at LNF ==
N/A

== Description of the activity ==
The goal of the experiment associated to this proposal is to measure the toroidal current driven by each of the two neutral beams (NBCD). To this end, it is important to achieve long NBI plasmas with stable density.
Long pulses are needed to approach the current stabilization phase and stable density ensures that the time dependence of the toroidal current is mainly due to its
electrodynamic evolution and is not caused by a different coupling of the beam power issued from variations in the thermal plasma parameters. Additional ECRH power can be used for
density control purposes. Plasmas with co-NBI (NBI1) and counter-NBI (NBI2), as well as plasmas with balanced injection (NBI1+NBI2), will be explored. The level of optimum ECRH power will be determined depending
on the operation conditions considering that moderate electron temperature (below 800 keV) are desirable to favour shorter stabilization times. Using off-axis ECRH injection may also help to reduce L/R time.
The measured toroidal current will be compared to the computational/numerical estimates of the toroidal current generated by both neutrals beams.

However, since both bootstrap and NBCD are contributing to the toroidal plasma current, the validation of NBCD needs first a numerical computation of the bootstrap contribution, ideally with a validated tool.
Validating bootstrap current is a long standing issue in TJ-II ECRH plasmas. Experimental proposals devoted to this task have been unsuccessful because of the difficulties encountered to achieve pulses long enough to observe current stabilization. Two days are requested to carry out this proposal. In its first part, and following the procedure described in http://fusionwiki.ciemat.es/wiki/TJ-II:Validation_of_bootstrap_predictions (Velasco et al.), we will
carry out an attempt to achieve long ECRH pulses, looking for a current stabilization phase, in order to fulfill as best as possible the goals detailed in the proposal by Velasco et al. If proved unfeasible, we will switch to NBI plasmas and carry out the rest of the experiments.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==

Required resources:
* Number of plasma discharges or days of operation: 2 days.
* Essential diagnostic systems: Rogowski (Ip), Microwave Interferometer, Scattering Thomson (ne & Te), Doppler Reflectometry (Er), ECE (Te), NPA (Ti), MSE (rotational transform)
* Type of plasmas (heating configuration): NBI plasmas with background ECRH power for density control purposes
* Specific requirements on wall conditioning if any: Density control and long pulses are critical for this proposal.
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: N/A

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II: Validation of neutral beam current drive

2022-01-21T14:03:31Z

Acappa: /* Description of the activity */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Validation of neutral beam current drive'''

== Name and affiliation of proponent ==
A. Cappa, S. Mulas, M. Liniers, T. Estrada, E. Ascasibar, J. Velasco et al.

== Details of contact person at LNF ==
N/A

== Description of the activity ==
The goal of the experiment associated to this proposal is to measure the toroidal current driven by each of the two neutral beams (NBCD). To this end, it is important to achieve long NBI plasmas with stable density.
Long pulses are needed to approach the current stabilization phase and stable density ensures that the time dependence of the toroidal current is mainly due to its
electrodynamic evolution and is not caused by a different coupling of the beam power issued from variations in the thermal plasma parameters. Additional ECRH power can be used for
density control purposes. Plasmas with co-NBI (NBI1) and counter-NBI (NBI2), as well as plasmas with balanced injection (NBI1+NBI2), will be explored. The level of optimum ECRH power will be determined depending
on the operation conditions considering that moderate electron temperature (below 800 keV) are desirable to favour shorter stabilization times. Using off-axis ECRH injection may also help to reduce L/R time.
The measured toroidal current will be compared to the computational/numerical estimates of the toroidal current generated by both neutrals beams.

However, since both bootstrap and NBCD are contributing to the toroidal plasma current, the validation of NBCD needs first a numerical computation of the bootstrap contribution, ideally with a validated tool.
Validating bootstrap current is a long standing issue in TJ-II ECRH plasmas. Experimental proposals devoted to this task have been unsuccessful because of the difficulties encountered to achieve pulses long enough to observe current stabilization. Two days are requested to carry out this proposal. In its first part, and following the procedure described in http://fusionwiki.ciemat.es/wiki/TJ-II:Validation_of_bootstrap_predictions (Velasco et al.), we will
carry out an attempt to achieve long ECRH pulses, looking for a current stabilization phase, in order to fulfill as best as possible the goals detailed in the proposal by Velasco et al. If proved unfeasible, we will switch to NBI plasmas and carry out the rest of the experiments.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==

Required resources:
* Number of plasma discharges or days of operation: 2 days.
* Essential diagnostic systems: Rogowski (Ip), Microwave Interferometer, Scattering Thomson (ne & Te), Doppler Reflectometry (Er), ECE (Te), NPA (Ti), MSE (rotational transform)
* Type of plasmas (heating configuration): NBI plasmas with background ECRH power for density control purposes
* Specific requirements on wall conditioning if any: Density control and long pulses are critical for this proposal.
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: N/A

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II: Validation of neutral beam current drive

2022-01-21T14:03:00Z

Acappa: /* Description of the activity */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Validation of neutral beam current drive'''

== Name and affiliation of proponent ==
A. Cappa, S. Mulas, M. Liniers, T. Estrada, E. Ascasibar, J. Velasco et al.

== Details of contact person at LNF ==
N/A

== Description of the activity ==
The goal of the experiment associated to this proposal is to measure the toroidal current driven by each of the two neutral beams (NBCD). To this end, it is important to achieve long NBI plasmas with stable density.
Long pulses are needed to approach the current stabilization phase and stable density ensures that the time dependence of the toroidal current is mainly due to its
electrodynamic evolution and is not caused by a different coupling of the beam power issued from variations in the thermal plasma parameters. Additional ECRH power can be used for
density control purposes. Plasmas with co-NBI (NBI1) and counter-NBI (NBI2), as well as plasmas with balanced injection (NBI1+NBI2), will be explored. The level of optimum ECRH power will be determined depending
on the operation conditions considering that moderate electron temperature (below 800 keV) are desirable to favour shorter stabilization times. Using off-axis ECRH injection may also help to reduce L/R time.
The measured toroidal current will be compared to the computational/numerical estimates of the toroidal current generated by both neutrals beams.

However, since both bootstrap and NBCD are contributing to the toroidal plasma current, the validation of NBCD needs first a numerical computation of the bootstrap contribution, ideally with a validated tool.
Validating bootstrap current is a long standing issue in TJ-II ECRH plasmas. Experimental proposals devoted to this task have been unsuccessful because of the difficulties encountered to achieve pulses long enough to observe current stabilization. Two days are requested to carry out this proposal. In its first part, and following the procedure described in http://fusionwiki.ciemat.es/wiki/TJ-II:Validation_of_bootstrap_predictions (Velasco et al.), we will
carry out an attempt to achieve long ECRH pulses, looking for a current stabilization phase, in order to fulfill as best as possible the goals detailed in the proposal by Velasco et al. If proved unfeasible, we will switch to NBI plasma and carry out the rest of the experiments.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==

Required resources:
* Number of plasma discharges or days of operation: 2 days.
* Essential diagnostic systems: Rogowski (Ip), Microwave Interferometer, Scattering Thomson (ne & Te), Doppler Reflectometry (Er), ECE (Te), NPA (Ti), MSE (rotational transform)
* Type of plasmas (heating configuration): NBI plasmas with background ECRH power for density control purposes
* Specific requirements on wall conditioning if any: Density control and long pulses are critical for this proposal.
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: N/A

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II: Validation of neutral beam current drive

2022-01-21T14:02:29Z

Acappa: /* Description of the activity */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Validation of neutral beam current drive'''

== Name and affiliation of proponent ==
A. Cappa, S. Mulas, M. Liniers, T. Estrada, E. Ascasibar, J. Velasco et al.

== Details of contact person at LNF ==
N/A

== Description of the activity ==
The goal of the experiment associated to this proposal is to measure the toroidal current driven by each of the two neutral beams (NBCD). To this end, it is important to achieve long NBI plasmas with stable density.
Long pulses are needed to approach the current stabilization phase and stable density ensures that the time dependence of the toroidal current is mainly due to its
electrodynamic evolution and is not caused by a different coupling of the beam power issued from variations in the thermal plasma parameters. Additional ECRH power can be used for
density control purposes. Plasmas with co-NBI (NBI1) and counter-NBI (NBI2), as well as plasmas with balanced injection (NBI1+NBI2), will be explored. The level of optimum ECRH power will be determined depending
on the operation conditions considering that moderate electron temperature (below 800 keV) are desirable to favour shorter stabilization times. Using off-axis ECRH injection may also help to reduce L/R time.
The measured toroidal current will be compared to the computational/numerical estimates of the toroidal current generated by both neutrals beams.

However, since both bootstrap and NBCD are contributing to the toroidal plasma current, the validation of NBCD needs first a numerical computation of the bootstrap contribution, ideally with a validated tool.
Validating bootstrap current is a long standing issue in TJ-II ECRH plasmas. Experimental proposals devoted to this task have been unsuccessful because of the difficulties encountered to achieve pulses long enough to observe current stabilization. Two days are requested to carry out this proposal. In its first part, and following the procedure described in http://fusionwiki.ciemat.es/wiki/TJ-II:Validation_of_bootstrap_predictions (Velasco et al.), we will
carry out an attempt to achieve long ECRH pulses, looking for a current stabilization phase, in order to fulfill as best the possible the goals detailed in the proposal by Velasco et al. If proved unfeasible, we will switch to NBI plasma and carry out the rest of the experiments.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==

Required resources:
* Number of plasma discharges or days of operation: 2 days.
* Essential diagnostic systems: Rogowski (Ip), Microwave Interferometer, Scattering Thomson (ne & Te), Doppler Reflectometry (Er), ECE (Te), NPA (Ti), MSE (rotational transform)
* Type of plasmas (heating configuration): NBI plasmas with background ECRH power for density control purposes
* Specific requirements on wall conditioning if any: Density control and long pulses are critical for this proposal.
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: N/A

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II: Validation of neutral beam current drive

2022-01-21T14:01:06Z

Acappa: /* Description of required resources */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Validation of neutral beam current drive'''

== Name and affiliation of proponent ==
A. Cappa, S. Mulas, M. Liniers, T. Estrada, E. Ascasibar, J. Velasco et al.

== Details of contact person at LNF ==
N/A

== Description of the activity ==
The goal of the experiment associated to this proposal is to measure the toroidal current driven by each of the two neutral beams (NBCD). To this end, it is important to achieve long NBI plasmas with stable density.
Long pulses are needed to approach the current stabilization phase and stable density ensures that the time dependence of the toroidal current is mainly due to its
electrodynamic evolution and is not caused by a different coupling of the beam power issued from variations in the thermal plasma parameters. Additional ECRH power can be used for
density control purposes. Plasmas with co-NBI (NBI1) and counter-NBI (NBI2), as well as plasmas with balanced injection (NBI1+NBI2), will be explored. The level of optimum ECRH power will be determined depending
on the operation conditions considering that moderate electron temperature (below 800 keV) are desirable to favour shorter stabilization times. Using off-axis ECRH injection may also help to reduce L/R time.
The measured toroidal current will be compared to the computational/numerical estimates of the toroidal current generated by both neutrals beams.

However, since both bootstrap and NBCD are contributing to the toroidal plasma current, the validation of NBCD needs first a numerical computation of the bootstrap contribution, ideally with a validated tool.
Validating bootstrap current is a long standing issue in TJ-II ECRH plasmas. Experimental proposals devoted to this task have been unsuccessful because of the difficulties encountered to achieve pulses long enough to observe current stabilization. Two day are requested to carry out this proposal. In its first part, and following the procedure described in http://fusionwiki.ciemat.es/wiki/TJ-II:Validation_of_bootstrap_predictions (Velasco et al.), we will
carry out an attempt to achieve long ECRH pulses, looking for a current stabilization phase, in order to fulfill as best the possible the goals detailed in the proposal by Velasco et al. If proved unfeasible, we will switch to NBI plasma and carry out the rest of the experiments.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==

Required resources:
* Number of plasma discharges or days of operation: 2 days.
* Essential diagnostic systems: Rogowski (Ip), Microwave Interferometer, Scattering Thomson (ne & Te), Doppler Reflectometry (Er), ECE (Te), NPA (Ti), MSE (rotational transform)
* Type of plasmas (heating configuration): NBI plasmas with background ECRH power for density control purposes
* Specific requirements on wall conditioning if any: Density control and long pulses are critical for this proposal.
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: N/A

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II: Validation of neutral beam current drive

2022-01-21T14:00:29Z

Acappa: /* Description of the activity */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Validation of neutral beam current drive'''

== Name and affiliation of proponent ==
A. Cappa, S. Mulas, M. Liniers, T. Estrada, E. Ascasibar, J. Velasco et al.

== Details of contact person at LNF ==
N/A

== Description of the activity ==
The goal of the experiment associated to this proposal is to measure the toroidal current driven by each of the two neutral beams (NBCD). To this end, it is important to achieve long NBI plasmas with stable density.
Long pulses are needed to approach the current stabilization phase and stable density ensures that the time dependence of the toroidal current is mainly due to its
electrodynamic evolution and is not caused by a different coupling of the beam power issued from variations in the thermal plasma parameters. Additional ECRH power can be used for
density control purposes. Plasmas with co-NBI (NBI1) and counter-NBI (NBI2), as well as plasmas with balanced injection (NBI1+NBI2), will be explored. The level of optimum ECRH power will be determined depending
on the operation conditions considering that moderate electron temperature (below 800 keV) are desirable to favour shorter stabilization times. Using off-axis ECRH injection may also help to reduce L/R time.
The measured toroidal current will be compared to the computational/numerical estimates of the toroidal current generated by both neutrals beams.

However, since both bootstrap and NBCD are contributing to the toroidal plasma current, the validation of NBCD needs first a numerical computation of the bootstrap contribution, ideally with a validated tool.
Validating bootstrap current is a long standing issue in TJ-II ECRH plasmas. Experimental proposals devoted to this task have been unsuccessful because of the difficulties encountered to achieve pulses long enough to observe current stabilization. Two day are requested to carry out this proposal. In its first part, and following the procedure described in http://fusionwiki.ciemat.es/wiki/TJ-II:Validation_of_bootstrap_predictions (Velasco et al.), we will
carry out an attempt to achieve long ECRH pulses, looking for a current stabilization phase, in order to fulfill as best the possible the goals detailed in the proposal by Velasco et al. If proved unfeasible, we will switch to NBI plasma and carry out the rest of the experiments.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==

Required resources:
* Number of plasma discharges or days of operation: 1
* Essential diagnostic systems: Rogowski (Ip), Microwave Interferometer, Scattering Thomson (ne & Te), Doppler Reflectometry (Er), ECE (Te), NPA (Ti), MSE (rotational transform)
* Type of plasmas (heating configuration): NBI plasmas with background ECRH power for density control purposes
* Specific requirements on wall conditioning if any: Density control and long pulses are critical for this proposal.
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: N/A

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II: Validation of neutral beam current drive

2022-01-21T13:59:33Z

Acappa: /* Description of the activity */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Validation of neutral beam current drive'''

== Name and affiliation of proponent ==
A. Cappa, S. Mulas, M. Liniers, T. Estrada, E. Ascasibar, J. Velasco et al.

== Details of contact person at LNF ==
N/A

== Description of the activity ==
The goal of the experiment associated to this proposal is to measure the toroidal current driven by each of the two neutral beams (NBCD). To this end, it is important to achieve long NBI plasmas with stable density.
Long pulses are needed to approach the current stabilization phase and stable density ensures that the time dependence of the toroidal current is mainly due to its
electrodynamic evolution and is not caused by a different coupling of the beam power issued from variations in the thermal plasma parameters. Additional ECRH power can be used for
density control purposes. Plasmas with co-NBI (NBI1) and counter-NBI (NBI2), as well as plasmas with balanced injection (NBI1+NBI2), will be explored. The level of optimum ECRH power will be determined depending
on the operation conditions considering that moderate electron temperature (below 800 keV) are desirable to favour shorter stabilization times. Using off-axis ECRH injection may also help to reduce L/R time.
The measured toroidal current will be compared to the computational/numerical estimates of the toroidal current generated by both neutrals beams once the bootstrap current contribution is removed.

However, since both bootstrap and NBCD are contributing to the toroidal plasma current, the validation of NBCD needs first a numerical computation of the bootstrap contribution, ideally with a validated tool.
Validating bootstrap current is a long standing issue in TJ-II ECRH plasmas. Experimental proposals devoted to this task have been unsuccessful because of the difficulties encountered to achieve pulses long enough to observe current stabilization. Two day are requested to carry out this proposal. In its first part, and following the procedure described in http://fusionwiki.ciemat.es/wiki/TJ-II:Validation_of_bootstrap_predictions (Velasco et al.), we will
carry out an attempt to achieve long ECRH pulses, looking for a current stabilization phase, in order to fulfill as best the possible the goals detailed in the proposal by Velasco et al. If proved unfeasible, we will switch to NBI plasma and carry out the rest of the experiments.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==

Required resources:
* Number of plasma discharges or days of operation: 1
* Essential diagnostic systems: Rogowski (Ip), Microwave Interferometer, Scattering Thomson (ne & Te), Doppler Reflectometry (Er), ECE (Te), NPA (Ti), MSE (rotational transform)
* Type of plasmas (heating configuration): NBI plasmas with background ECRH power for density control purposes
* Specific requirements on wall conditioning if any: Density control and long pulses are critical for this proposal.
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: N/A

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II: Validation of neutral beam current drive

2022-01-21T13:49:27Z

Acappa: /* Description of the activity */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Validation of neutral beam current drive'''

== Name and affiliation of proponent ==
A. Cappa, S. Mulas, M. Liniers, T. Estrada, E. Ascasibar, J. Velasco et al.

== Details of contact person at LNF ==
N/A

== Description of the activity ==
The goal of the experiment associated to this proposal is to measure the toroidal current driven by each of the two neutral beams (NBCD). To this end, it is important to achieve long NBI plasmas with stable density.
Long pulses are needed to approach the current stabilization phase and stable density ensures that the time dependence of the toroidal current is mainly due to its
electrodynamic evolution and is not caused by a different coupling of the beam power issued from variations in the thermal plasma parameters. Additional ECRH power can be used for
density control purposes. Plasmas with co-NBI (NBI1) and counter-NBI (NBI2), as well as plasmas with balanced injection (NBI1+NBI2), will be explored. The level of optimum ECRH power will be determined depending
on the operation conditions considering that moderate electron temperature (below 800 keV) are desirable to favour shorter stabilization times. Using off-axis ECRH injection may also help to reduce L/R time.

Since both bootstrap and NBCD are contributing to the toroidal plasma current, the validation of NBCD needs first an estimation of the bootstrap contribution. Validating bootstrap current is a long standing
issue in TJ-II ECRH plasmas. Experimental proposals devoted to this task (http://fusionwiki.ciemat.es/wiki/TJ-II:Validation_of_bootstrap_predictions) have been unsuccessful because of the difficulties encountered to achieve pulses long enough to observe current stabilization.

The measured toroidal current will be compared to the computational/numerical estimates of the toroidal current generated by both neutrals beams once the bootstrap current contribution is removed.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==

Required resources:
* Number of plasma discharges or days of operation: 1
* Essential diagnostic systems: Rogowski (Ip), Microwave Interferometer, Scattering Thomson (ne & Te), Doppler Reflectometry (Er), ECE (Te), NPA (Ti), MSE (rotational transform)
* Type of plasmas (heating configuration): NBI plasmas with background ECRH power for density control purposes
* Specific requirements on wall conditioning if any: Density control and long pulses are critical for this proposal.
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: N/A

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II: Validation of neutral beam current drive

2022-01-21T13:30:54Z

Acappa: /* Description of the activity */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Validation of neutral beam current drive'''

== Name and affiliation of proponent ==
A. Cappa, S. Mulas, M. Liniers, T. Estrada, E. Ascasibar, J. Velasco et al.

== Details of contact person at LNF ==
N/A

== Description of the activity ==
The goal of the experiment associated to this proposal is to measure the toroidal current driven by each of the two neutral beams. To this end, it is important to achieve long NBI plasmas with stable density.
Long pulses are needed to approach the current stabilization phase and stable density ensures that the time dependence of the toroidal current is mainly due to its
electrodynamic evolution and is not caused by a different coupling of the beam power issued from variations in the thermal plasma parameters. Additional ECRH power can be used for
density control purposes. Plasmas with co-NBI (NBI1) and counter-NBI (NBI2), as well as plasmas with balanced injection (NBI1+NBI2), will be explored. The level of optimum ECRH power will be determined depending
on the operation conditions considering that moderate electron temperature (below 800 keV) are desirable to favour shorter stabilization times. Using off-axis ECRH injection may also help to reduce L/R time.

The measured toroidal current will be compared to the computational/numerical estimates of the toroidal current generated by both neutrals beams once the bootstrap current contribution is removed.
http://fusionwiki.ciemat.es/wiki/TJ-II:Validation_of_bootstrap_predictions

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==

Required resources:
* Number of plasma discharges or days of operation: 1
* Essential diagnostic systems: Rogowski (Ip), Microwave Interferometer, Scattering Thomson (ne & Te), Doppler Reflectometry (Er), ECE (Te), NPA (Ti), MSE (rotational transform)
* Type of plasmas (heating configuration): NBI plasmas with background ECRH power for density control purposes
* Specific requirements on wall conditioning if any: Density control and long pulses are critical for this proposal.
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: N/A

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II:Searching for AEs suppression scenarios using off-axis ECCD

2022-01-20T16:49:25Z

Acappa: /* Name and affiliation of proponent */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Searching for AEs suppression scenarios using off-axis ECCD'''

== Name and affiliation of proponent ==
Á. Cappa, J. Martínez, E. Ascasíbar, P. Pons, T. Estrada, D. Zarzoso, C. Hidalgo

== Details of contact person at LNF ==
If applicable, enter contact person here or write N/A

== Description of the activity ==
The goal of the proposal is to find ECRH launching configurations for which the amplitude of
NBI-driven Alfvén Eigenmodes (AEs) is mitigated. Besides the interest that such scenarios have for the fast particles topic, studies of coupling between NBI-driven AEs and low frequency zonal flows may also benefit from them.
Many scenarios making use of different "control" parameters
have already been tested in past experimental sessions, showing always strong changes in AEs activity.
Plasma density variations and changes of the rotational transform profile due to the
many contributions to the total plasma current (NBCD, ECCD, Bootstrap current) are the parameters
with the higher impact. However, although inducing modifications in the general spectrum of the excited modes,
none of the investigated scenarios show a clear possibility to suppress AEs without inducing large
changes in plasma parameters, being the most promising the one employing ECCD.
In this particular case we intend to investigate the effect of
off-axis ECCD at different plasma radius.

== Experimental plan ==

[[File:imagen1.png |thumb|right|300px| Figure 1. Heating scheme. ECH1 beam, used to induce current, is
launched with two different power levels for gyrotron stability purposes]]

Until now, only ECCD on-axis has been investigated. We will now try to modify the rotational transform profile by inducing ECCD off-axis with
different levels of power at different plasma radius. '''The success of the proposal depends on whether or not the gyrotron that will be used to drive the current (ECH1) can be operated as shown in figure 1'''. To this end, previous tube conditionning sessions will be needed to ensure that the gyrotron can work with different levels of anode voltage in the same shot and thus deliver different levels of power. The heating power set-up shown in figure 1 will allow us to investigate the effect of ECCD using different combinations of ECH1 beam power and ECCD efficiency.
With this set-up, ECH2 power (always with <math>n_{||}=0</math>) is used for start-up and density control in the NBI phase. Ideally, there should be no power in the first gyrotron until the central part of the NBI phase, in which the reference shot with <math>n_{||}=0</math> in ECH1 will be compared to the shots obtained by changing the injection direction of ECH1. For stability purposes of the gyrotron, and depending on the result of the conditionning tests, a small amount of power may be required from the begginning of the shot until higher power is requested.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==
Required resources:
* Number of plasma discharges or days of operation: One day - 20 useful shots
* Essential diagnostic systems: Besides the common shot to shot diagnostics (ECE, Thomson, Interferometry, Radiation), all systems providing edge plasma profiles are needed. Moreover, HIBP, Doppler Reflectometer, Mirnov coils (both helical and poloidal arrays) and CNPA meaurements are mandatory. MSE would also be desirable to measure changes induced by ECCD.
* Type of plasmas (heating configuration): ECRH + NBI-1 hydrogen plasmas following the heating scheme shown in Figure 1.
* Specific requirements on wall conditioning if any:
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: no

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II: Validation of neutral beam current drive

2022-01-20T16:40:34Z

Acappa: /* Description of the activity */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Validation of neutral beam current drive'''

== Name and affiliation of proponent ==
A. Cappa, S. Mulas, M. Liniers, T. Estrada, E. Ascasibar, J. Velasco et al.

== Details of contact person at LNF ==
N/A

== Description of the activity ==
The goal of the experiment associated to this proposal is to measure the toroidal current driven by each of the two neutral beams. To this end, it is important to achieve long NBI plasmas with stable density.
Long pulses are needed to approach the current stabilization phase and stable density ensures that the time dependence of the toroidal current is mainly due to its
electrodynamic evolution and is not caused by a different coupling of the beam power issued from variations in the thermal plasma parameters. Additional ECRH power can be used for
density control purposes. Plasmas with co-NBI (NBI1) and counter-NBI (NBI2), as well as plasmas with balanced injection (NBI1+NBI2), will be explored. The level of optimum ECRH power will be determined depending
on the operation conditions considering that moderate electron temperature (below 800 keV) are desirable to favour shorter stabilization times. Using off-axis ECRH injection may also help to reduce L/R time.

The measured toroidal current will be compared to the computational/numerical estimates of the toroidal current generated by both neutrals beams once the bootstrap current contribution is removed.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==

Required resources:
* Number of plasma discharges or days of operation: 1
* Essential diagnostic systems: Rogowski (Ip), Microwave Interferometer, Scattering Thomson (ne & Te), Doppler Reflectometry (Er), ECE (Te), NPA (Ti), MSE (rotational transform)
* Type of plasmas (heating configuration): NBI plasmas with background ECRH power for density control purposes
* Specific requirements on wall conditioning if any: Density control and long pulses are critical for this proposal.
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: N/A

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II:Searching for AEs suppression scenarios using off-axis ECCD

2022-01-20T16:29:50Z

Acappa: /* Description of required resources */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Searching for AEs suppression scenarios using off-axis ECCD'''

== Name and affiliation of proponent ==
Á. Cappa, J. Martínez, E. Ascasíbar, P. Pons

== Details of contact person at LNF ==
If applicable, enter contact person here or write N/A

== Description of the activity ==
The goal of the proposal is to find ECRH launching configurations for which the amplitude of
NBI-driven Alfvén Eigenmodes (AEs) is mitigated. Besides the interest that such scenarios have for the fast particles topic, studies of coupling between NBI-driven AEs and low frequency zonal flows may also benefit from them.
Many scenarios making use of different "control" parameters
have already been tested in past experimental sessions, showing always strong changes in AEs activity.
Plasma density variations and changes of the rotational transform profile due to the
many contributions to the total plasma current (NBCD, ECCD, Bootstrap current) are the parameters
with the higher impact. However, although inducing modifications in the general spectrum of the excited modes,
none of the investigated scenarios show a clear possibility to suppress AEs without inducing large
changes in plasma parameters, being the most promising the one employing ECCD.
In this particular case we intend to investigate the effect of
off-axis ECCD at different plasma radius.

== Experimental plan ==

[[File:imagen1.png |thumb|right|300px| Figure 1. Heating scheme. ECH1 beam, used to induce current, is
launched with two different power levels for gyrotron stability purposes]]

Until now, only ECCD on-axis has been investigated. We will now try to modify the rotational transform profile by inducing ECCD off-axis with
different levels of power at different plasma radius. '''The success of the proposal depends on whether or not the gyrotron that will be used to drive the current (ECH1) can be operated as shown in figure 1'''. To this end, previous tube conditionning sessions will be needed to ensure that the gyrotron can work with different levels of anode voltage in the same shot and thus deliver different levels of power. The heating power set-up shown in figure 1 will allow us to investigate the effect of ECCD using different combinations of ECH1 beam power and ECCD efficiency.
With this set-up, ECH2 power (always with <math>n_{||}=0</math>) is used for start-up and density control in the NBI phase. Ideally, there should be no power in the first gyrotron until the central part of the NBI phase, in which the reference shot with <math>n_{||}=0</math> in ECH1 will be compared to the shots obtained by changing the injection direction of ECH1. For stability purposes of the gyrotron, and depending on the result of the conditionning tests, a small amount of power may required from the begginning of the shot until higher power is requested.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==
Required resources:
* Number of plasma discharges or days of operation: One day - 20 useful shots
* Essential diagnostic systems: Besides the common shot to shot diagnostics (ECE, Thomson, Interferometry, Radiation), all systems providing edge plasma profiles are needed. Moreover, HIBP, Doppler Reflectometer, Mirnov coils (both helical and poloidal arrays) and CNPA meaurements are mandatory. MSE would also be desirable to measure changes induced by ECCD.
* Type of plasmas (heating configuration): ECRH + NBI-1 hydrogen plasmas following the heating scheme shown in Figure 1.
* Specific requirements on wall conditioning if any:
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: no

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II:Searching for AEs suppression scenarios using off-axis ECCD

2022-01-20T16:16:16Z

Acappa: /* Experimental plan */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Searching for AEs suppression scenarios using off-axis ECCD'''

== Name and affiliation of proponent ==
Á. Cappa, J. Martínez, E. Ascasíbar, P. Pons

== Details of contact person at LNF ==
If applicable, enter contact person here or write N/A

== Description of the activity ==
The goal of the proposal is to find ECRH launching configurations for which the amplitude of
NBI-driven Alfvén Eigenmodes (AEs) is mitigated. Besides the interest that such scenarios have for the fast particles topic, studies of coupling between NBI-driven AEs and low frequency zonal flows may also benefit from them.
Many scenarios making use of different "control" parameters
have already been tested in past experimental sessions, showing always strong changes in AEs activity.
Plasma density variations and changes of the rotational transform profile due to the
many contributions to the total plasma current (NBCD, ECCD, Bootstrap current) are the parameters
with the higher impact. However, although inducing modifications in the general spectrum of the excited modes,
none of the investigated scenarios show a clear possibility to suppress AEs without inducing large
changes in plasma parameters, being the most promising the one employing ECCD.
In this particular case we intend to investigate the effect of
off-axis ECCD at different plasma radius.

== Experimental plan ==

[[File:imagen1.png |thumb|right|300px| Figure 1. Heating scheme. ECH1 beam, used to induce current, is
launched with two different power levels for gyrotron stability purposes]]

Until now, only ECCD on-axis has been investigated. We will now try to modify the rotational transform profile by inducing ECCD off-axis with
different levels of power at different plasma radius. '''The success of the proposal depends on whether or not the gyrotron that will be used to drive the current (ECH1) can be operated as shown in figure 1'''. To this end, previous tube conditionning sessions will be needed to ensure that the gyrotron can work with different levels of anode voltage in the same shot and thus deliver different levels of power. The heating power set-up shown in figure 1 will allow us to investigate the effect of ECCD using different combinations of ECH1 beam power and ECCD efficiency.
With this set-up, ECH2 power (always with <math>n_{||}=0</math>) is used for start-up and density control in the NBI phase. Ideally, there should be no power in the first gyrotron until the central part of the NBI phase, in which the reference shot with <math>n_{||}=0</math> in ECH1 will be compared to the shots obtained by changing the injection direction of ECH1. For stability purposes of the gyrotron, and depending on the result of the conditionning tests, a small amount of power may required from the begginning of the shot until higher power is requested.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==
Required resources:
* Number of plasma discharges or days of operation: One day - 20 useful shots
* Essential diagnostic systems: Besides the common shot to shot diagnostics (ECE, Thomson, Interferometry, Radiation), all systems providing edge plasma profiles are needed. Moreover, HIBP, Doppler Reflectometer, Mirnov coils (both helicoidal and poloidal arrays) and CNPA meaurements are mandatory. MSE would also be desirable to measure changes induced by ECCD.
* Type of plasmas (heating configuration): ECRH + NBI-1 hydrogen plasmas following the heating scheme shown in Figure 1.
* Specific requirements on wall conditioning if any:
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: no

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II:Searching for AEs suppression scenarios using off-axis ECCD

2022-01-20T16:13:37Z

Acappa: /* Experimental plan */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Searching for AEs suppression scenarios using off-axis ECCD'''

== Name and affiliation of proponent ==
Á. Cappa, J. Martínez, E. Ascasíbar, P. Pons

== Details of contact person at LNF ==
If applicable, enter contact person here or write N/A

== Description of the activity ==
The goal of the proposal is to find ECRH launching configurations for which the amplitude of
NBI-driven Alfvén Eigenmodes (AEs) is mitigated. Besides the interest that such scenarios have for the fast particles topic, studies of coupling between NBI-driven AEs and low frequency zonal flows may also benefit from them.
Many scenarios making use of different "control" parameters
have already been tested in past experimental sessions, showing always strong changes in AEs activity.
Plasma density variations and changes of the rotational transform profile due to the
many contributions to the total plasma current (NBCD, ECCD, Bootstrap current) are the parameters
with the higher impact. However, although inducing modifications in the general spectrum of the excited modes,
none of the investigated scenarios show a clear possibility to suppress AEs without inducing large
changes in plasma parameters, being the most promising the one employing ECCD.
In this particular case we intend to investigate the effect of
off-axis ECCD at different plasma radius.

== Experimental plan ==

[[File:imagen1.png |thumb|right|300px| Figure 1. Heating scheme. ECH1 beam, used to induce current, is
launched with two different power levels for gyrotron stability purposes]]

Until now, only ECCD on-axis has been investigated. We will now try to modify the rotational transform profile by inducing ECCD off-axis with
different levels of power at different plasma radius. '''The success of the proposal depends on whether or not the gyrotron that will be used to drive the current (ECH1) can be operated as shown in figure 1'''. To this end, previous tube conditionning sessions will be needed to ensure that the gyrotron can work with different levels of anode voltage in the same shot and thus deliver different levels of power. The heating power set-up shown in figure 1 will allow us to investigate the effect of ECCD using different combinations of ECH1 beam power and ECCD efficiency.
With this set-up, ECH2 power (always with <math>n_{||}=0</math>) is used for start-up and density control in the NBI phase. Ideally, there should be no power in the first gyrotron until the central part of the NBI phase, in which the reference shot with <math>n_{||}=0</math> in ECH1 will be compared to the shots obtained by changing the injection direction of ECH1. For stability purposes ECH1, depending on the result of the conditionning tests, a small amount of power may required from the begginning of the shot until higher power is requested.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==
Required resources:
* Number of plasma discharges or days of operation: One day - 20 useful shots
* Essential diagnostic systems: Besides the common shot to shot diagnostics (ECE, Thomson, Interferometry, Radiation), all systems providing edge plasma profiles are needed. Moreover, HIBP, Doppler Reflectometer, Mirnov coils (both helicoidal and poloidal arrays) and CNPA meaurements are mandatory. MSE would also be desirable to measure changes induced by ECCD.
* Type of plasmas (heating configuration): ECRH + NBI-1 hydrogen plasmas following the heating scheme shown in Figure 1.
* Specific requirements on wall conditioning if any:
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: no

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II:Searching for AEs suppression scenarios using off-axis ECCD

2022-01-20T16:12:43Z

Acappa: /* Experimental plan */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Searching for AEs suppression scenarios using off-axis ECCD'''

== Name and affiliation of proponent ==
Á. Cappa, J. Martínez, E. Ascasíbar, P. Pons

== Details of contact person at LNF ==
If applicable, enter contact person here or write N/A

== Description of the activity ==
The goal of the proposal is to find ECRH launching configurations for which the amplitude of
NBI-driven Alfvén Eigenmodes (AEs) is mitigated. Besides the interest that such scenarios have for the fast particles topic, studies of coupling between NBI-driven AEs and low frequency zonal flows may also benefit from them.
Many scenarios making use of different "control" parameters
have already been tested in past experimental sessions, showing always strong changes in AEs activity.
Plasma density variations and changes of the rotational transform profile due to the
many contributions to the total plasma current (NBCD, ECCD, Bootstrap current) are the parameters
with the higher impact. However, although inducing modifications in the general spectrum of the excited modes,
none of the investigated scenarios show a clear possibility to suppress AEs without inducing large
changes in plasma parameters, being the most promising the one employing ECCD.
In this particular case we intend to investigate the effect of
off-axis ECCD at different plasma radius.

== Experimental plan ==

[[File:imagen1.png |thumb|right|300px| Figure 1. Heating scheme. ECH1 beam, used to induce current, is
launched with two different power levels for gyrotron stability purposes]]

Until now, only ECCD on-axis has been investigated. We will now try to modify the rotational transform profile by inducing ECCD off-axis with
different levels of power at different plasma radius. The success of the proposal depends on whether or not the gyrotron that will be used to drive the current (ECH1) can be operated as shown in figure 1. To this end, previous tube conditionning sessions will be needed to ensure that the gyrotron can work with different levels of anode voltage in the same shot and thus deliver different levels of power. The heating power set-up shown in figure 1 will allow us to investigate the effect of ECCD using different combinations of ECH1 beam power and ECCD efficiency.
With this set-up, ECH2 power (always with <math>n_{||}=0</math>) is used for start-up and density control in the NBI phase. Ideally, there should be no power in the first gyrotron until the central part of the NBI phase, in which the reference shot with <math>n_{||}=0</math> in ECH1 will be compared to the shots obtained by changing the injection direction of ECH1. For stability purposes ECH1, depending on the result of the conditionning tests, a small amount of power may required from the begginning of the shot until higher power is requested.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==
Required resources:
* Number of plasma discharges or days of operation: One day - 20 useful shots
* Essential diagnostic systems: Besides the common shot to shot diagnostics (ECE, Thomson, Interferometry, Radiation), all systems providing edge plasma profiles are needed. Moreover, HIBP, Doppler Reflectometer, Mirnov coils (both helicoidal and poloidal arrays) and CNPA meaurements are mandatory. MSE would also be desirable to measure changes induced by ECCD.
* Type of plasmas (heating configuration): ECRH + NBI-1 hydrogen plasmas following the heating scheme shown in Figure 1.
* Specific requirements on wall conditioning if any:
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: no

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II:Searching for AEs suppression scenarios using off-axis ECCD

2022-01-20T16:10:03Z

Acappa: /* Experimental plan */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Searching for AEs suppression scenarios using off-axis ECCD'''

== Name and affiliation of proponent ==
Á. Cappa, J. Martínez, E. Ascasíbar, P. Pons

== Details of contact person at LNF ==
If applicable, enter contact person here or write N/A

== Description of the activity ==
The goal of the proposal is to find ECRH launching configurations for which the amplitude of
NBI-driven Alfvén Eigenmodes (AEs) is mitigated. Besides the interest that such scenarios have for the fast particles topic, studies of coupling between NBI-driven AEs and low frequency zonal flows may also benefit from them.
Many scenarios making use of different "control" parameters
have already been tested in past experimental sessions, showing always strong changes in AEs activity.
Plasma density variations and changes of the rotational transform profile due to the
many contributions to the total plasma current (NBCD, ECCD, Bootstrap current) are the parameters
with the higher impact. However, although inducing modifications in the general spectrum of the excited modes,
none of the investigated scenarios show a clear possibility to suppress AEs without inducing large
changes in plasma parameters, being the most promising the one employing ECCD.
In this particular case we intend to investigate the effect of
off-axis ECCD at different plasma radius.

== Experimental plan ==

[[File:imagen1.png |thumb|right|300px| Figure 1. Heating scheme. ECH1 beam, used to induce current, is
launched with two different power levels for gyrotron stability purposes]]

Until now, only ECCD on-axis has been investigated. We will now try to modify the rotational transform profile by inducing ECCD off-axis with
different levels of power at different plasma radius. The success of the proposal depends on whether or not the gyrotron that will be used to drive the current (ECH1) can be operated as shown in figure 1. To this end, previous tube conditionning sessions will be needed to ensure that the gyrotron can work with different levels of anode voltage in the same shot and thus deliver different levels of power. The heating power set-up shown in figure 1 will allow us to investigate the effect of ECCD using different combinations of ECH1 beam power and ECCD efficiency.
With this set-up, ECH2 power (always with <math>n_{||}=0</math>) is used for start-up and density control in the NBI phase. Ideally, there should be no power in the first gyrotron until the central part of the NBI phase, in which the reference shot with <math>n_{||}=0</math> in ECH1 will be compared to the shots obtained by changing the injection direction of ECH1.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==
Required resources:
* Number of plasma discharges or days of operation: One day - 20 useful shots
* Essential diagnostic systems: Besides the common shot to shot diagnostics (ECE, Thomson, Interferometry, Radiation), all systems providing edge plasma profiles are needed. Moreover, HIBP, Doppler Reflectometer, Mirnov coils (both helicoidal and poloidal arrays) and CNPA meaurements are mandatory. MSE would also be desirable to measure changes induced by ECCD.
* Type of plasmas (heating configuration): ECRH + NBI-1 hydrogen plasmas following the heating scheme shown in Figure 1.
* Specific requirements on wall conditioning if any:
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: no

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II:Searching for AEs suppression scenarios using off-axis ECCD

2022-01-20T16:08:45Z

Acappa: /* Experimental plan */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Searching for AEs suppression scenarios using off-axis ECCD'''

== Name and affiliation of proponent ==
Á. Cappa, J. Martínez, E. Ascasíbar, P. Pons

== Details of contact person at LNF ==
If applicable, enter contact person here or write N/A

== Description of the activity ==
The goal of the proposal is to find ECRH launching configurations for which the amplitude of
NBI-driven Alfvén Eigenmodes (AEs) is mitigated. Besides the interest that such scenarios have for the fast particles topic, studies of coupling between NBI-driven AEs and low frequency zonal flows may also benefit from them.
Many scenarios making use of different "control" parameters
have already been tested in past experimental sessions, showing always strong changes in AEs activity.
Plasma density variations and changes of the rotational transform profile due to the
many contributions to the total plasma current (NBCD, ECCD, Bootstrap current) are the parameters
with the higher impact. However, although inducing modifications in the general spectrum of the excited modes,
none of the investigated scenarios show a clear possibility to suppress AEs without inducing large
changes in plasma parameters, being the most promising the one employing ECCD.
In this particular case we intend to investigate the effect of
off-axis ECCD at different plasma radius.

== Experimental plan ==

[[File:imagen1.png |thumb|right|300px| Figure 1. Heating scheme. ECH1 beam, used to induce current, is
launched with two different power levels for gyrotron stability purposes]]

Until now, only ECCD on-axis has been investigated. We will now try to modify the rotational transform profile by inducing ECCD off-axis with
different levels of power at different plasma radius. The success of the proposal depends on whether or not the gyrotron that will be used to drive the current (ECH1) can be operated as shown in figure 1. To this end, previous tube conditionning sessions will be needed to ensure that the gyrotron can work with different levels of anode voltage in the same shot and thus deliver different levels of power. The heating power set-up shown in figure 1 will allow us to investigate the effect of ECCD using different combinations of ECH1 beam power and ECCD efficiency.
With this set-up, ECH2 power (always with <math>n_{||}=0</math>) is used for start-up and density control in the NBI phase. Ideally, there should be no power in the first gyrotron until the central part of the NBI phase, in which the reference shot with <math>n_{||}=0</math> in ECH1 will be compared to the shots obtained by changing the injection directyion of ECH1.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==
Required resources:
* Number of plasma discharges or days of operation: One day - 20 useful shots
* Essential diagnostic systems: Besides the common shot to shot diagnostics (ECE, Thomson, Interferometry, Radiation), all systems providing edge plasma profiles are needed. Moreover, HIBP, Doppler Reflectometer, Mirnov coils (both helicoidal and poloidal arrays) and CNPA meaurements are mandatory. MSE would also be desirable to measure changes induced by ECCD.
* Type of plasmas (heating configuration): ECRH + NBI-1 hydrogen plasmas following the heating scheme shown in Figure 1.
* Specific requirements on wall conditioning if any:
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: no

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II:Searching for AEs suppression scenarios using off-axis ECCD

2022-01-20T16:08:07Z

Acappa: /* Experimental plan */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Searching for AEs suppression scenarios using off-axis ECCD'''

== Name and affiliation of proponent ==
Á. Cappa, J. Martínez, E. Ascasíbar, P. Pons

== Details of contact person at LNF ==
If applicable, enter contact person here or write N/A

== Description of the activity ==
The goal of the proposal is to find ECRH launching configurations for which the amplitude of
NBI-driven Alfvén Eigenmodes (AEs) is mitigated. Besides the interest that such scenarios have for the fast particles topic, studies of coupling between NBI-driven AEs and low frequency zonal flows may also benefit from them.
Many scenarios making use of different "control" parameters
have already been tested in past experimental sessions, showing always strong changes in AEs activity.
Plasma density variations and changes of the rotational transform profile due to the
many contributions to the total plasma current (NBCD, ECCD, Bootstrap current) are the parameters
with the higher impact. However, although inducing modifications in the general spectrum of the excited modes,
none of the investigated scenarios show a clear possibility to suppress AEs without inducing large
changes in plasma parameters, being the most promising the one employing ECCD.
In this particular case we intend to investigate the effect of
off-axis ECCD at different plasma radius.

== Experimental plan ==

[[File:imagen1.png |thumb|right|300px| Figure 1. Heating scheme. ECH1 beam, used to induce current, is
launched with two different power levels for gyrotron stability purposes]]

Until now, only ECCD on-axis has been investigated. We will now try to modify the rotational transform profile by inducing ECCD off-axis with
different levels of power at different plasma radius. The success of the proposal depends on whether or not the gyrotron that will be used to drive the current can be operated as shown in figure 1. To this end, previous tube conditionning sessions will be needed to ensure that the gyrotron can work with different levels of anode voltage in the same shot and thus deliver different levels of power. The heating power set-up shown in figure 1 will allow us to investigate the effect of ECCD using different combinations of ECH1 beam power and ECCD efficiency.
With this set-up, ECH2 power (always with <math>n_{||}=0</math>) is used for start-up and density control in the NBI phase. Ideally, there should be no power in the first gyrotron until the central part of the NBI phase, in which the reference shot with <math>n_{||}=0</math> in ECH1 will be compared to the shots obtained by changing the injection directyion of ECH1.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==
Required resources:
* Number of plasma discharges or days of operation: One day - 20 useful shots
* Essential diagnostic systems: Besides the common shot to shot diagnostics (ECE, Thomson, Interferometry, Radiation), all systems providing edge plasma profiles are needed. Moreover, HIBP, Doppler Reflectometer, Mirnov coils (both helicoidal and poloidal arrays) and CNPA meaurements are mandatory. MSE would also be desirable to measure changes induced by ECCD.
* Type of plasmas (heating configuration): ECRH + NBI-1 hydrogen plasmas following the heating scheme shown in Figure 1.
* Specific requirements on wall conditioning if any:
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: no

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II:Searching for AEs suppression scenarios using off-axis ECCD

2022-01-20T16:03:22Z

Acappa: /* Experimental plan */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Searching for AEs suppression scenarios using off-axis ECCD'''

== Name and affiliation of proponent ==
Á. Cappa, J. Martínez, E. Ascasíbar, P. Pons

== Details of contact person at LNF ==
If applicable, enter contact person here or write N/A

== Description of the activity ==
The goal of the proposal is to find ECRH launching configurations for which the amplitude of
NBI-driven Alfvén Eigenmodes (AEs) is mitigated. Besides the interest that such scenarios have for the fast particles topic, studies of coupling between NBI-driven AEs and low frequency zonal flows may also benefit from them.
Many scenarios making use of different "control" parameters
have already been tested in past experimental sessions, showing always strong changes in AEs activity.
Plasma density variations and changes of the rotational transform profile due to the
many contributions to the total plasma current (NBCD, ECCD, Bootstrap current) are the parameters
with the higher impact. However, although inducing modifications in the general spectrum of the excited modes,
none of the investigated scenarios show a clear possibility to suppress AEs without inducing large
changes in plasma parameters, being the most promising the one employing ECCD.
In this particular case we intend to investigate the effect of
off-axis ECCD at different plasma radius.

== Experimental plan ==

[[File:imagen1.png |thumb|right|300px| Figure 1. Heating scheme. ECH1 beam, used to induce current, is
launched with two different power levels for gyrotron stability purposes]]

Until now, only ECCD on-axis has been investigated. We will now try to modify the rotational transform profile by inducing ECCD off-axis with
different levels of power at different plasma radius. The success of the proposal depends on whether or not the gyrotron that will be used to drive the current can be operated as shown in figure 1. To this end, previous tube conditionning sessions will be needed to ensure that the gyrotron can work with different levels of anode voltage in the same shot and thus deliver different levels of power. The heating power set-up shown in figure 1 will allow us to investigate the effect of ECCD using different combinations of ECH1 beam power and ECCD efficiency.
With this set-up, launching ECH2 power with <math>n_{||}=0</math> , only a small amount of ECCD current will be induced by the
ECH1 beam during the ECRH phase while the larger amount of ECCD will be induced during the NBI phase by increasing the ECH1 beam power. For stability purposes ECH1 must be working at low power from the begginning of the shot until higher power is requested.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==
Required resources:
* Number of plasma discharges or days of operation: One day - 20 useful shots
* Essential diagnostic systems: Besides the common shot to shot diagnostics (ECE, Thomson, Interferometry, Radiation), all systems providing edge plasma profiles are needed. Moreover, HIBP, Doppler Reflectometer, Mirnov coils (both helicoidal and poloidal arrays) and CNPA meaurements are mandatory. MSE would also be desirable to measure changes induced by ECCD.
* Type of plasmas (heating configuration): ECRH + NBI-1 hydrogen plasmas following the heating scheme shown in Figure 1.
* Specific requirements on wall conditioning if any:
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: no

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II:Searching for AEs suppression scenarios using off-axis ECCD

2022-01-20T15:59:36Z

Acappa: /* Description of the activity */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Searching for AEs suppression scenarios using off-axis ECCD'''

== Name and affiliation of proponent ==
Á. Cappa, J. Martínez, E. Ascasíbar, P. Pons

== Details of contact person at LNF ==
If applicable, enter contact person here or write N/A

== Description of the activity ==
The goal of the proposal is to find ECRH launching configurations for which the amplitude of
NBI-driven Alfvén Eigenmodes (AEs) is mitigated. Besides the interest that such scenarios have for the fast particles topic, studies of coupling between NBI-driven AEs and low frequency zonal flows may also benefit from them.
Many scenarios making use of different "control" parameters
have already been tested in past experimental sessions, showing always strong changes in AEs activity.
Plasma density variations and changes of the rotational transform profile due to the
many contributions to the total plasma current (NBCD, ECCD, Bootstrap current) are the parameters
with the higher impact. However, although inducing modifications in the general spectrum of the excited modes,
none of the investigated scenarios show a clear possibility to suppress AEs without inducing large
changes in plasma parameters, being the most promising the one employing ECCD.
In this particular case we intend to investigate the effect of
off-axis ECCD at different plasma radius.

== Experimental plan ==

[[File:imagen1.png |thumb|right|300px| Figure 1. Heating scheme. ECH1 beam, used to induce current, is
launched with two different power levels for gyrotron stability purposes]]

Until now, only ECCD on-axis has been investigated. We will now try to modify the rotational transform profile by inducing ECCD off-axis with
different levels of power at different plasma radius. The success of the proposal depends on whether or not the gyrotron that will inject the current can be operated as shown in the figure
Teo set-ups can be ased to carry out this experiment

The heating power set-up shown in figure 1 will allow
us to investigate the effect of ECCD using different combinations of ECH1 beam power and ECCD efficiency.
With this set-up, launching ECH2 power with <math>n_{||}=0</math> , only a small amount of ECCD current will be induced by the
ECH1 beam during the ECRH phase while the larger amount of ECCD will be induced during the NBI phase by increasing the ECH1 beam power. For stability purposes ECH1 must be working at low power from the begginning of the shot until higher power is requested.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==
Required resources:
* Number of plasma discharges or days of operation: One day - 20 useful shots
* Essential diagnostic systems: Besides the common shot to shot diagnostics (ECE, Thomson, Interferometry, Radiation), all systems providing edge plasma profiles are needed. Moreover, HIBP, Doppler Reflectometer, Mirnov coils (both helicoidal and poloidal arrays) and CNPA meaurements are mandatory. MSE would also be desirable to measure changes induced by ECCD.
* Type of plasmas (heating configuration): ECRH + NBI-1 hydrogen plasmas following the heating scheme shown in Figure 1.
* Specific requirements on wall conditioning if any:
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: no

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II:Searching for AEs suppression scenarios using off-axis ECCD

2022-01-20T15:59:18Z

Acappa: /* Experimental plan */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Searching for AEs suppression scenarios using off-axis ECCD'''

== Name and affiliation of proponent ==
Á. Cappa, J. Martínez, E. Ascasíbar, P. Pons

== Details of contact person at LNF ==
If applicable, enter contact person here or write N/A

== Description of the activity ==
The goal of the proposal is to find ECRH launching configurations for which the amplitude of
NBI-driven Alfvén Eigenmodes (AEs) is mitigated. Besides the interest that such scenarios have for the fast particles topic, studies of coupling between NBI-driven AEs and low frequency zonal flows may also benefit from them.
Many scenarios making use of different "control" parameters
have already been tested in past experimental sessions, showing always strong changes in AEs activity.
Plasma density variations and changes of the rotational transform profile due to the
many contributions to the total plasma current (NBCD, ECCD, Bootstrap current) are the parameters
with the higher impact. However, although inducing modifications in the general spectrum of the excited modes,
none of the investigated scenarios show a clear possibility to suppress AEs without inducing large
changes in plasma parameters, being the most promising the one employing ECCD.
In this particular case we intend to investigate the effect of
off-axis ECCD at different plasma radius. The success of the proposal depends on whether or not the gyrotron that will inject the current can be operated as shown in the figure

== Experimental plan ==

[[File:imagen1.png |thumb|right|300px| Figure 1. Heating scheme. ECH1 beam, used to induce current, is
launched with two different power levels for gyrotron stability purposes]]

Until now, only ECCD on-axis has been investigated. We will now try to modify the rotational transform profile by inducing ECCD off-axis with
different levels of power at different plasma radius. The success of the proposal depends on whether or not the gyrotron that will inject the current can be operated as shown in the figure
Teo set-ups can be ased to carry out this experiment

The heating power set-up shown in figure 1 will allow
us to investigate the effect of ECCD using different combinations of ECH1 beam power and ECCD efficiency.
With this set-up, launching ECH2 power with <math>n_{||}=0</math> , only a small amount of ECCD current will be induced by the
ECH1 beam during the ECRH phase while the larger amount of ECCD will be induced during the NBI phase by increasing the ECH1 beam power. For stability purposes ECH1 must be working at low power from the begginning of the shot until higher power is requested.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==
Required resources:
* Number of plasma discharges or days of operation: One day - 20 useful shots
* Essential diagnostic systems: Besides the common shot to shot diagnostics (ECE, Thomson, Interferometry, Radiation), all systems providing edge plasma profiles are needed. Moreover, HIBP, Doppler Reflectometer, Mirnov coils (both helicoidal and poloidal arrays) and CNPA meaurements are mandatory. MSE would also be desirable to measure changes induced by ECCD.
* Type of plasmas (heating configuration): ECRH + NBI-1 hydrogen plasmas following the heating scheme shown in Figure 1.
* Specific requirements on wall conditioning if any:
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: no

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II:Searching for AEs suppression scenarios using off-axis ECCD

2022-01-20T15:59:04Z

Acappa: /* Description of the activity */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Searching for AEs suppression scenarios using off-axis ECCD'''

== Name and affiliation of proponent ==
Á. Cappa, J. Martínez, E. Ascasíbar, P. Pons

== Details of contact person at LNF ==
If applicable, enter contact person here or write N/A

== Description of the activity ==
The goal of the proposal is to find ECRH launching configurations for which the amplitude of
NBI-driven Alfvén Eigenmodes (AEs) is mitigated. Besides the interest that such scenarios have for the fast particles topic, studies of coupling between NBI-driven AEs and low frequency zonal flows may also benefit from them.
Many scenarios making use of different "control" parameters
have already been tested in past experimental sessions, showing always strong changes in AEs activity.
Plasma density variations and changes of the rotational transform profile due to the
many contributions to the total plasma current (NBCD, ECCD, Bootstrap current) are the parameters
with the higher impact. However, although inducing modifications in the general spectrum of the excited modes,
none of the investigated scenarios show a clear possibility to suppress AEs without inducing large
changes in plasma parameters, being the most promising the one employing ECCD.
In this particular case we intend to investigate the effect of
off-axis ECCD at different plasma radius. The success of the proposal depends on whether or not the gyrotron that will inject the current can be operated as shown in the figure

== Experimental plan ==

[[File:imagen1.png |thumb|right|300px| Figure 1. Heating scheme. ECH1 beam, used to induce current, is
launched with two different power levels for gyrotron stability purposes]]

Until now, only ECCD on-axis has been investigated. We will now try to modify the rotational transform profile by inducing ECCD off-axis with
different levels of power at different plasma radius. Teo set-ups can be ased to carry out this experiment

The heating power set-up shown in figure 1 will allow
us to investigate the effect of ECCD using different combinations of ECH1 beam power and ECCD efficiency.
With this set-up, launching ECH2 power with <math>n_{||}=0</math> , only a small amount of ECCD current will be induced by the
ECH1 beam during the ECRH phase while the larger amount of ECCD will be induced during the NBI phase by increasing the ECH1 beam power. For stability purposes ECH1 must be working at low power from the begginning of the shot until higher power is requested.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==
Required resources:
* Number of plasma discharges or days of operation: One day - 20 useful shots
* Essential diagnostic systems: Besides the common shot to shot diagnostics (ECE, Thomson, Interferometry, Radiation), all systems providing edge plasma profiles are needed. Moreover, HIBP, Doppler Reflectometer, Mirnov coils (both helicoidal and poloidal arrays) and CNPA meaurements are mandatory. MSE would also be desirable to measure changes induced by ECCD.
* Type of plasmas (heating configuration): ECRH + NBI-1 hydrogen plasmas following the heating scheme shown in Figure 1.
* Specific requirements on wall conditioning if any:
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: no

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II:Searching for AEs suppression scenarios using off-axis ECCD

2022-01-20T15:57:04Z

Acappa: /* Experimental plan */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Searching for AEs suppression scenarios using off-axis ECCD'''

== Name and affiliation of proponent ==
Á. Cappa, J. Martínez, E. Ascasíbar, P. Pons

== Details of contact person at LNF ==
If applicable, enter contact person here or write N/A

== Description of the activity ==
The goal of the proposal is to find ECRH launching configurations for which the amplitude of
NBI-driven Alfvén Eigenmodes (AEs) is mitigated. Besides the interest that such scenarios have for the fast particles topic, studies of coupling between NBI-driven AEs and low frequency zonal flows may also benefit from them.
Many scenarios making use of different "control" parameters
have already been tested in past experimental sessions, showing always strong changes in AEs activity.
Plasma density variations and changes of the rotational transform profile due to the
many contributions to the total plasma current (NBCD, ECCD, Bootstrap current) are the parameters
with the higher impact. However, although inducing modifications in the general spectrum of the excited modes,
none of the investigated scenarios show a clear possibility to suppress AEs without inducing large
changes in plasma parameters, being the most promising the one employing ECCD.
In this particular case we intend to investigate the effect of
off-axis ECCD at different plasma radius.

== Experimental plan ==

[[File:imagen1.png |thumb|right|300px| Figure 1. Heating scheme. ECH1 beam, used to induce current, is
launched with two different power levels for gyrotron stability purposes]]

Until now, only ECCD on-axis has been investigated. We will now try to modify the rotational transform profile by inducing ECCD off-axis with
different levels of power at different plasma radius. Teo set-ups can be ased to carry out this experiment

The heating power set-up shown in figure 1 will allow
us to investigate the effect of ECCD using different combinations of ECH1 beam power and ECCD efficiency.
With this set-up, launching ECH2 power with <math>n_{||}=0</math> , only a small amount of ECCD current will be induced by the
ECH1 beam during the ECRH phase while the larger amount of ECCD will be induced during the NBI phase by increasing the ECH1 beam power. For stability purposes ECH1 must be working at low power from the begginning of the shot until higher power is requested.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==
Required resources:
* Number of plasma discharges or days of operation: One day - 20 useful shots
* Essential diagnostic systems: Besides the common shot to shot diagnostics (ECE, Thomson, Interferometry, Radiation), all systems providing edge plasma profiles are needed. Moreover, HIBP, Doppler Reflectometer, Mirnov coils (both helicoidal and poloidal arrays) and CNPA meaurements are mandatory. MSE would also be desirable to measure changes induced by ECCD.
* Type of plasmas (heating configuration): ECRH + NBI-1 hydrogen plasmas following the heating scheme shown in Figure 1.
* Specific requirements on wall conditioning if any:
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: no

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II:Searching for AEs suppression scenarios using off-axis ECCD

2022-01-20T15:47:27Z

Acappa: /* Description of the activity */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Searching for AEs suppression scenarios using off-axis ECCD'''

== Name and affiliation of proponent ==
Á. Cappa, J. Martínez, E. Ascasíbar, P. Pons

== Details of contact person at LNF ==
If applicable, enter contact person here or write N/A

== Description of the activity ==
The goal of the proposal is to find ECRH launching configurations for which the amplitude of
NBI-driven Alfvén Eigenmodes (AEs) is mitigated. Besides the interest that such scenarios have for the fast particles topic, studies of coupling between NBI-driven AEs and low frequency zonal flows may also benefit from them.
Many scenarios making use of different "control" parameters
have already been tested in past experimental sessions, showing always strong changes in AEs activity.
Plasma density variations and changes of the rotational transform profile due to the
many contributions to the total plasma current (NBCD, ECCD, Bootstrap current) are the parameters
with the higher impact. However, although inducing modifications in the general spectrum of the excited modes,
none of the investigated scenarios show a clear possibility to suppress AEs without inducing large
changes in plasma parameters, being the most promising the one employing ECCD.
In this particular case we intend to investigate the effect of
off-axis ECCD at different plasma radius.

== Experimental plan ==

[[File:imagen1.png |thumb|right|300px| Figure 1. Heating scheme. ECH1 beam, used to induce current, is
launched with two different power levels for gyrotron stability purposes]]

Until now, only ECCD on-axis has been investigated. We will now try to modify the rotational transform profile by inducing ECCD off-axis with
different levels of power at different plasma radius. The heating power set-up shown in figure 1 will allow
us to investigate the effect of ECCD using different combinations of ECH1 beam power and ECCD efficiency.
With this set-up, launching ECH2 power with <math>n_{||}=0</math> , only a small amount of ECCD current will be induced by the
ECH1 beam during the ECRH phase while the larger amount of ECCD will be induced during the NBI phase by increasing the ECH1 beam power. For stability purposes ECH1 must be working at low power from the begginning of the shot until higher power is requested.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==
Required resources:
* Number of plasma discharges or days of operation: One day - 20 useful shots
* Essential diagnostic systems: Besides the common shot to shot diagnostics (ECE, Thomson, Interferometry, Radiation), all systems providing edge plasma profiles are needed. Moreover, HIBP, Doppler Reflectometer, Mirnov coils (both helicoidal and poloidal arrays) and CNPA meaurements are mandatory. MSE would also be desirable to measure changes induced by ECCD.
* Type of plasmas (heating configuration): ECRH + NBI-1 hydrogen plasmas following the heating scheme shown in Figure 1.
* Specific requirements on wall conditioning if any:
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: no

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II:Searching for AEs suppression scenarios using off-axis ECCD

2022-01-20T15:47:07Z

Acappa: /* Name and affiliation of proponent */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Searching for AEs suppression scenarios using off-axis ECCD'''

== Name and affiliation of proponent ==
Á. Cappa, J. Martínez, E. Ascasíbar, P. Pons

== Details of contact person at LNF ==
If applicable, enter contact person here or write N/A

== Description of the activity ==
Enter description here <ref>A. Einstein, Journal of Exceptional Results (2017)</ref>, including motivation/objectives and experience of the proponent (typically one-two pages)

The goal of the proposal is to find ECRH launching configurations for which the amplitude of
NBI-driven Alfvén Eigenmodes (AEs) is mitigated. Besides the interest that such scenarios have for the fast particles topic, studies of coupling between NBI-driven AEs and low frequency zonal flows may also benefit from them.
Many scenarios making use of different "control" parameters
have already been tested in past experimental sessions, showing always strong changes in AEs activity.
Plasma density variations and changes of the rotational transform profile due to the
many contributions to the total plasma current (NBCD, ECCD, Bootstrap current) are the parameters
with the higher impact. However, although inducing modifications in the general spectrum of the excited modes,
none of the investigated scenarios show a clear possibility to suppress AEs without inducing large
changes in plasma parameters, being the most promising the one employing ECCD.
In this particular case we intend to investigate the effect of
off-axis ECCD at different plasma radius.

== Experimental plan ==

[[File:imagen1.png |thumb|right|300px| Figure 1. Heating scheme. ECH1 beam, used to induce current, is
launched with two different power levels for gyrotron stability purposes]]

Until now, only ECCD on-axis has been investigated. We will now try to modify the rotational transform profile by inducing ECCD off-axis with
different levels of power at different plasma radius. The heating power set-up shown in figure 1 will allow
us to investigate the effect of ECCD using different combinations of ECH1 beam power and ECCD efficiency.
With this set-up, launching ECH2 power with <math>n_{||}=0</math> , only a small amount of ECCD current will be induced by the
ECH1 beam during the ECRH phase while the larger amount of ECCD will be induced during the NBI phase by increasing the ECH1 beam power. For stability purposes ECH1 must be working at low power from the begginning of the shot until higher power is requested.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==
Required resources:
* Number of plasma discharges or days of operation: One day - 20 useful shots
* Essential diagnostic systems: Besides the common shot to shot diagnostics (ECE, Thomson, Interferometry, Radiation), all systems providing edge plasma profiles are needed. Moreover, HIBP, Doppler Reflectometer, Mirnov coils (both helicoidal and poloidal arrays) and CNPA meaurements are mandatory. MSE would also be desirable to measure changes induced by ECCD.
* Type of plasmas (heating configuration): ECRH + NBI-1 hydrogen plasmas following the heating scheme shown in Figure 1.
* Specific requirements on wall conditioning if any:
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: no

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II:Searching for AEs suppression scenarios using off-axis ECCD

2022-01-20T15:44:19Z

Acappa: /* Description of required resources */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Searching for AEs suppression scenarios using off-axis ECCD'''

== Name and affiliation of proponent ==
Enter name, affiliation and ORCID code here

Suggested format:

[https://orcid.org/0000-0000-0000-0000 John Doe], University of Ivory Tower

== Details of contact person at LNF ==
If applicable, enter contact person here or write N/A

== Description of the activity ==
Enter description here <ref>A. Einstein, Journal of Exceptional Results (2017)</ref>, including motivation/objectives and experience of the proponent (typically one-two pages)

The goal of the proposal is to find ECRH launching configurations for which the amplitude of
NBI-driven Alfvén Eigenmodes (AEs) is mitigated. Besides the interest that such scenarios have for the fast particles topic, studies of coupling between NBI-driven AEs and low frequency zonal flows may also benefit from them.
Many scenarios making use of different "control" parameters
have already been tested in past experimental sessions, showing always strong changes in AEs activity.
Plasma density variations and changes of the rotational transform profile due to the
many contributions to the total plasma current (NBCD, ECCD, Bootstrap current) are the parameters
with the higher impact. However, although inducing modifications in the general spectrum of the excited modes,
none of the investigated scenarios show a clear possibility to suppress AEs without inducing large
changes in plasma parameters, being the most promising the one employing ECCD.
In this particular case we intend to investigate the effect of
off-axis ECCD at different plasma radius.

== Experimental plan ==

[[File:imagen1.png |thumb|right|300px| Figure 1. Heating scheme. ECH1 beam, used to induce current, is
launched with two different power levels for gyrotron stability purposes]]

Until now, only ECCD on-axis has been investigated. We will now try to modify the rotational transform profile by inducing ECCD off-axis with
different levels of power at different plasma radius. The heating power set-up shown in figure 1 will allow
us to investigate the effect of ECCD using different combinations of ECH1 beam power and ECCD efficiency.
With this set-up, launching ECH2 power with <math>n_{||}=0</math> , only a small amount of ECCD current will be induced by the
ECH1 beam during the ECRH phase while the larger amount of ECCD will be induced during the NBI phase by increasing the ECH1 beam power. For stability purposes ECH1 must be working at low power from the begginning of the shot until higher power is requested.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==
Required resources:
* Number of plasma discharges or days of operation: One day - 20 useful shots
* Essential diagnostic systems: Besides the common shot to shot diagnostics (ECE, Thomson, Interferometry, Radiation), all systems providing edge plasma profiles are needed. Moreover, HIBP, Doppler Reflectometer, Mirnov coils (both helicoidal and poloidal arrays) and CNPA meaurements are mandatory. MSE would also be desirable to measure changes induced by ECCD.
* Type of plasmas (heating configuration): ECRH + NBI-1 hydrogen plasmas following the heating scheme shown in Figure 1.
* Specific requirements on wall conditioning if any:
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: no

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II:Searching for AEs suppression scenarios using off-axis ECCD

2022-01-20T15:42:42Z

Acappa: /* Background */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Searching for AEs suppression scenarios using off-axis ECCD'''

== Name and affiliation of proponent ==
Enter name, affiliation and ORCID code here

Suggested format:

[https://orcid.org/0000-0000-0000-0000 John Doe], University of Ivory Tower

== Details of contact person at LNF ==
If applicable, enter contact person here or write N/A

== Description of the activity ==
Enter description here <ref>A. Einstein, Journal of Exceptional Results (2017)</ref>, including motivation/objectives and experience of the proponent (typically one-two pages)

The goal of the proposal is to find ECRH launching configurations for which the amplitude of
NBI-driven Alfvén Eigenmodes (AEs) is mitigated. Besides the interest that such scenarios have for the fast particles topic, studies of coupling between NBI-driven AEs and low frequency zonal flows may also benefit from them.
Many scenarios making use of different "control" parameters
have already been tested in past experimental sessions, showing always strong changes in AEs activity.
Plasma density variations and changes of the rotational transform profile due to the
many contributions to the total plasma current (NBCD, ECCD, Bootstrap current) are the parameters
with the higher impact. However, although inducing modifications in the general spectrum of the excited modes,
none of the investigated scenarios show a clear possibility to suppress AEs without inducing large
changes in plasma parameters, being the most promising the one employing ECCD.
In this particular case we intend to investigate the effect of
off-axis ECCD at different plasma radius.

== Experimental plan ==

[[File:imagen1.png |thumb|right|300px| Figure 1. Heating scheme. ECH1 beam, used to induce current, is
launched with two different power levels for gyrotron stability purposes]]

Until now, only ECCD on-axis has been investigated. We will now try to modify the rotational transform profile by inducing ECCD off-axis with
different levels of power at different plasma radius. The heating power set-up shown in figure 1 will allow
us to investigate the effect of ECCD using different combinations of ECH1 beam power and ECCD efficiency.
With this set-up, launching ECH2 power with <math>n_{||}=0</math> , only a small amount of ECCD current will be induced by the
ECH1 beam during the ECRH phase while the larger amount of ECCD will be induced during the NBI phase by increasing the ECH1 beam power. For stability purposes ECH1 must be working at low power from the begginning of the shot until higher power is requested.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==
Required resources:
* Number of plasma discharges or days of operation:
* Essential diagnostic systems:
* Type of plasmas (heating configuration):
* Specific requirements on wall conditioning if any:
* External users: need a local computer account for data access: yes/no
* Any external equipment to be integrated? Provide description and integration needs:

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II:Searching for AEs suppression scenarios using off-axis ECCD

2022-01-20T15:42:32Z

Acappa: /* Description of the activity */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Searching for AEs suppression scenarios using off-axis ECCD'''

== Name and affiliation of proponent ==
Enter name, affiliation and ORCID code here

Suggested format:

[https://orcid.org/0000-0000-0000-0000 John Doe], University of Ivory Tower

== Details of contact person at LNF ==
If applicable, enter contact person here or write N/A

== Description of the activity ==
Enter description here <ref>A. Einstein, Journal of Exceptional Results (2017)</ref>, including motivation/objectives and experience of the proponent (typically one-two pages)

The goal of the proposal is to find ECRH launching configurations for which the amplitude of
NBI-driven Alfvén Eigenmodes (AEs) is mitigated. Besides the interest that such scenarios have for the fast particles topic, studies of coupling between NBI-driven AEs and low frequency zonal flows may also benefit from them.
Many scenarios making use of different "control" parameters
have already been tested in past experimental sessions, showing always strong changes in AEs activity.
Plasma density variations and changes of the rotational transform profile due to the
many contributions to the total plasma current (NBCD, ECCD, Bootstrap current) are the parameters
with the higher impact. However, although inducing modifications in the general spectrum of the excited modes,
none of the investigated scenarios show a clear possibility to suppress AEs without inducing large
changes in plasma parameters, being the most promising the one employing ECCD.
In this particular case we intend to investigate the effect of
off-axis ECCD at different plasma radius.

== Background ==

The goal of the proposal is to find ECRH launching configurations for which the amplitude of
NBI-driven Alfvén Eigenmodes (AEs) is mitigated. Besides the interest that such scenarios have for the fast particles topic, studies of coupling between NBI-driven AEs and low frequency zonal flows may also benefit from them.
Many scenarios making use of different "control" parameters
have already been tested in past experimental sessions, showing always strong changes in AEs activity.
Plasma density variations and changes of the rotational transform profile due to the
many contributions to the total plasma current (NBCD, ECCD, Bootstrap current) are the parameters
with the higher impact. However, although inducing modifications in the general spectrum of the excited modes,
none of the investigated scenarios show a clear possibility to suppress AEs without inducing large
changes in plasma parameters, being the most promising the one employing ECCD.
In this particular case we intend to investigate the effect of
off-axis ECCD at different plasma radius.

== Experimental plan ==

[[File:imagen1.png |thumb|right|300px| Figure 1. Heating scheme. ECH1 beam, used to induce current, is
launched with two different power levels for gyrotron stability purposes]]

Until now, only ECCD on-axis has been investigated. We will now try to modify the rotational transform profile by inducing ECCD off-axis with
different levels of power at different plasma radius. The heating power set-up shown in figure 1 will allow
us to investigate the effect of ECCD using different combinations of ECH1 beam power and ECCD efficiency.
With this set-up, launching ECH2 power with <math>n_{||}=0</math> , only a small amount of ECCD current will be induced by the
ECH1 beam during the ECRH phase while the larger amount of ECCD will be induced during the NBI phase by increasing the ECH1 beam power. For stability purposes ECH1 must be working at low power from the begginning of the shot until higher power is requested.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==
Required resources:
* Number of plasma discharges or days of operation:
* Essential diagnostic systems:
* Type of plasmas (heating configuration):
* Specific requirements on wall conditioning if any:
* External users: need a local computer account for data access: yes/no
* Any external equipment to be integrated? Provide description and integration needs:

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II:Searching for AEs suppression scenarios using off-axis ECCD

2022-01-20T15:40:55Z

Acappa: /* Background */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Searching for AEs suppression scenarios using off-axis ECCD'''

== Name and affiliation of proponent ==
Enter name, affiliation and ORCID code here

Suggested format:

[https://orcid.org/0000-0000-0000-0000 John Doe], University of Ivory Tower

== Details of contact person at LNF ==
If applicable, enter contact person here or write N/A

== Description of the activity ==
Enter description here <ref>A. Einstein, Journal of Exceptional Results (2017)</ref>, including motivation/objectives and experience of the proponent (typically one-two pages)

== Background ==

The goal of the proposal is to find ECRH launching configurations for which the amplitude of
NBI-driven Alfvén Eigenmodes (AEs) is mitigated. Besides the interest that such scenarios have for the fast particles topic, studies of coupling between NBI-driven AEs and low frequency zonal flows may also benefit from them.
Many scenarios making use of different "control" parameters
have already been tested in past experimental sessions, showing always strong changes in AEs activity.
Plasma density variations and changes of the rotational transform profile due to the
many contributions to the total plasma current (NBCD, ECCD, Bootstrap current) are the parameters
with the higher impact. However, although inducing modifications in the general spectrum of the excited modes,
none of the investigated scenarios show a clear possibility to suppress AEs without inducing large
changes in plasma parameters, being the most promising the one employing ECCD.
In this particular case we intend to investigate the effect of
off-axis ECCD at different plasma radius.

== Experimental plan ==

[[File:imagen1.png |thumb|right|300px| Figure 1. Heating scheme. ECH1 beam, used to induce current, is
launched with two different power levels for gyrotron stability purposes]]

Until now, only ECCD on-axis has been investigated. We will now try to modify the rotational transform profile by inducing ECCD off-axis with
different levels of power at different plasma radius. The heating power set-up shown in figure 1 will allow
us to investigate the effect of ECCD using different combinations of ECH1 beam power and ECCD efficiency.
With this set-up, launching ECH2 power with <math>n_{||}=0</math> , only a small amount of ECCD current will be induced by the
ECH1 beam during the ECRH phase while the larger amount of ECCD will be induced during the NBI phase by increasing the ECH1 beam power. For stability purposes ECH1 must be working at low power from the begginning of the shot until higher power is requested.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==
Required resources:
* Number of plasma discharges or days of operation:
* Essential diagnostic systems:
* Type of plasmas (heating configuration):
* Specific requirements on wall conditioning if any:
* External users: need a local computer account for data access: yes/no
* Any external equipment to be integrated? Provide description and integration needs:

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II:Searching for AEs suppression scenarios using off-axis ECCD

2022-01-20T15:40:21Z

Acappa: /* Description of the activity */

TJ-II:Searching for AEs suppression scenarios using off-axis ECCD

2022-01-20T15:39:41Z

Acappa: /* Proposal title */

TJ-II:Searching for AEs suppression scenarios using off-axis ECCD

2022-01-20T15:39:17Z

TJ-II: Validation of neutral beam current drive

2022-01-18T15:34:58Z

Acappa: /* Description of required resources */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Validation of neutral beam current drive'''

== Name and affiliation of proponent ==
A. Cappa, S. Mulas, M. Liniers, T. Estrada, E. Ascasibar, J. Velasco et al.

== Details of contact person at LNF ==
N/A

== Description of the activity ==
The goal of the experiment associated to this proposal is to measure the toroidal current driven by each of the two neutral beams. To this end, it is important to achieve long NBI plasmas with stable density.
Long pulses are needed to approach the current stabilization phase and stable density ensures that the time dependence of the toroidal current is mainly due to its
electrodynamic evolution and is not caused by a different coupling of the beam power issued from variations in the thermal plasma parameters. Additional ECRH power can be used for
density control purposes. Plasmas with co-NBI (NBI1) and counter-NBI (NBI2), as well as plasmas with balanced injection (NBI1+NBI2), will be explored. The level of optimum ECRH power will be determined depending
on the operation conditions considering that moderate electron temperature (below 800 keV) are desirable to favour shorter stabilization times.

The measured toroidal current will be compared to the computational/numerical estimates of the toroidal current generated by both neutrals beams once the bootstrap current contribution is removed.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==

Required resources:
* Number of plasma discharges or days of operation: 1
* Essential diagnostic systems: Rogowski (Ip), Microwave Interferometer, Scattering Thomson (ne & Te), Doppler Reflectometry (Er), ECE (Te), NPA (Ti), MSE (rotational transform)
* Type of plasmas (heating configuration): NBI plasmas with background ECRH power for density control purposes
* Specific requirements on wall conditioning if any: Density control and long pulses are critical for this proposal.
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: N/A

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II: Validation of neutral beam current drive

2022-01-18T15:22:16Z

Acappa: /* Name and affiliation of proponent */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Validation of neutral beam current drive'''

== Name and affiliation of proponent ==
A. Cappa, S. Mulas, M. Liniers, T. Estrada, E. Ascasibar, J. Velasco et al.

== Details of contact person at LNF ==
N/A

== Description of the activity ==
The goal of the experiment associated to this proposal is to measure the toroidal current driven by each of the two neutral beams. To this end, it is important to achieve long NBI plasmas with stable density.
Long pulses are needed to approach the current stabilization phase and stable density ensures that the time dependence of the toroidal current is mainly due to its
electrodynamic evolution and is not caused by a different coupling of the beam power issued from variations in the thermal plasma parameters. Additional ECRH power can be used for
density control purposes. Plasmas with co-NBI (NBI1) and counter-NBI (NBI2), as well as plasmas with balanced injection (NBI1+NBI2), will be explored. The level of optimum ECRH power will be determined depending
on the operation conditions considering that moderate electron temperature (below 800 keV) are desirable to favour shorter stabilization times.

The measured toroidal current will be compared to the computational/numerical estimates of the toroidal current generated by both neutrals beams once the bootstrap current contribution is removed.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==

Required resources:
* Number of plasma discharges or days of operation: 1
* Essential diagnostic systems: Rogowski (Ip), Scattering Thomson (ne & Te), Doppler Reflectometry (Er), ECE (Te), NPA (Ti), MSE (rotational transform)
* Type of plasmas (heating configuration): NBI plasmas with background ECRH power for density control purposes
* Specific requirements on wall conditioning if any: Density control and long pulses are critical for this proposal.
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: N/A

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II: Validation of neutral beam current drive

2022-01-18T15:16:02Z

Acappa: /* Name and affiliation of proponent */

== Experimental campaign ==
Spring 2022

== Proposal title ==
'''Validation of neutral beam current drive'''

== Name and affiliation of proponent ==
A. Cappa, S. Mulas, M. Liniers, T. Estrada, E. Ascasibar, J. Velasco

== Details of contact person at LNF ==
N/A

== Description of the activity ==
The goal of the experiment associated to this proposal is to measure the toroidal current driven by each of the two neutral beams. To this end, it is important to achieve long NBI plasmas with stable density.
Long pulses are needed to approach the current stabilization phase and stable density ensures that the time dependence of the toroidal current is mainly due to its
electrodynamic evolution and is not caused by a different coupling of the beam power issued from variations in the thermal plasma parameters. Additional ECRH power can be used for
density control purposes. Plasmas with co-NBI (NBI1) and counter-NBI (NBI2), as well as plasmas with balanced injection (NBI1+NBI2), will be explored. The level of optimum ECRH power will be determined depending
on the operation conditions considering that moderate electron temperature (below 800 keV) are desirable to favour shorter stabilization times.

The measured toroidal current will be compared to the computational/numerical estimates of the toroidal current generated by both neutrals beams once the bootstrap current contribution is removed.

== International or National funding project or entity ==
Include funding here (grants, national plans)

== Description of required resources ==

Required resources:
* Number of plasma discharges or days of operation: 1
* Essential diagnostic systems: Rogowski (Ip), Scattering Thomson (ne & Te), Doppler Reflectometry (Er), ECE (Te), NPA (Ti), MSE (rotational transform)
* Type of plasmas (heating configuration): NBI plasmas with background ECRH power for density control purposes
* Specific requirements on wall conditioning if any: Density control and long pulses are critical for this proposal.
* External users: need a local computer account for data access: no
* Any external equipment to be integrated? Provide description and integration needs: N/A

== Preferred dates and degree of flexibility ==
Preferred dates: (format dd-mm-yyyy)


== References ==
<references />

<hr>
[[TJ-II:Experimental proposals|Back to list of experimental proposals]]

[[Category:TJ-II internal documents]]
[[Category:TJ-II experimental proposals Spring 2022]]

TJ-II: Validation of neutral beam current drive

2022-01-18T15:09:40Z

Acappa: /* Description of required resources */

TJ-II: Validation of neutral beam current drive

2022-01-18T15:00:50Z

Acappa: /* Description of required resources */

TJ-II: Validation of neutral beam current drive

2022-01-18T14:59:18Z

Acappa: /* Name and affiliation of proponent */

TJ-II: Validation of neutral beam current drive

2022-01-18T14:58:18Z

Acappa: /* Name and affiliation of proponent */