FusionWiki - User contributions [en]

LNF: Investigación, diseño, Estudio y Ensayo de componentes sometidos a Entornos EXtremos para validación industrial de Tecnologías de Envolturas REgeneradoras asociadas al desarrollo de REactores de fusión Magnética (E4XTREM)

2025-12-12T14:59:56Z

Elena.delaluna: /* LNF - Nationally funded project */

== LNF - Nationally funded project ==

'''Title''': '''Investigación, diseño, Estudio y Ensayo de componentes sometidos a Entornos EXtremos para validación industrial de Tecnologías de Envolturas REgeneradoras asociadas al desarrollo de REactores de fusión Magnética (E4XTREM)'''

'''Reference''': PLEC2024-011136 (Transmisiones) & MIG-20242101 (CDTI)

'''Programme and date''': Programa de Transferencia y Colaboración del Plan Estatal de Investigación Científica, Técnica y de Innovación 2024-2027.

'''Programme type (Modalidad de proyecto)''': Programa “Misiones de Ciencia e Innovación - Transmisiones” del año 2024 (PLEC2024-011136)

Proyecto MIG-20242101 subvencionado por CDTI – Centro de Desarrollo Tecnológico y la Innovación

'''Area/subarea (Área temática / subárea)''':

'''Principal Investigator(s)''': [https://orcid.org/0000-0001-8725-8167 Iole Palermo]

'''Project type''': Proyecto coordinado

'''Start-end dates''': 01/01/2025 - 21/12/2028

'''Financing granted (direct costs)''': 4.446.236 € (de los cuales 462.736 € son para el CIEMAT)

{| class="wikitable"
! Proyecto PLEC2024-011136 financiado por MICIU /AEI /10.13039/501100011033/ FEDER, UE !! Proyecto MIG-20242101 subvencionado por CDTI – Centro de Desarrollo Tecnológico y la Innovación
|-
| [[File:LogoOficial_PlanNacional_2021.png|500px]]
| [[File:CDTI_Logo.png|500px]]
|}

== Description of the project ==

The [https://projects.ciemat.es/es/web/e4xtrem/inicio E4XTREM project] falls under Thematic Priority 1 established in the TRANSMISIONES 2024 Programme: “Boosting the development of a Spanish fusion industry: advancing technologies that pave the way toward fusion.”

The project focuses primarily on Breeding Blanket technologies and on the development of auxiliary facilities with advanced testing capabilities, enabling Spanish industry to contribute high-value innovation to the development of fusion devices.

E4XTREM addresses novel, high-impact challenges. Its key ideas and primary objectives include:

*Construction of a pilot facility capable of hosting prototypes of various kinds: FASTER (Facility to Support Tritium Breeding Technology Experimental Research). This installation will enable the testing and functional validation of critical systems and components for future fusion reactors (from TRL0 to TRL4).
*Design of an irradiation module for IFMIF-DONES to test Breeding Blanket technologies (TRL2 to TRL3).
*Construction of a simplified prototype (test module) of a breeding system (BB/TBM type or irradiation module) to be tested in FASTER (TRL0 to TRL4).
*Development of new coatings for fusion environments (TRL3 to TRL4).

== Project documentation ==

(Optional) Add the project proposal and the final report at the end of the project, and any other information related with the project

== Main results ==

Enter text here (summary of main project results from the final report)

== Dissemination of project results (peer-reviewed publications and conference presentations) ==



== References ==
<references />


<hr>
[[LNF:Nationally Funded Projects|Back to list of nationally funded projects]]

[[Category:LNF Nationally Funded Projects]]

LNF: Investigación, diseño, Estudio y Ensayo de componentes sometidos a Entornos EXtremos para validación industrial de Tecnologías de Envolturas REgeneradoras asociadas al desarrollo de REactores de fusión Magnética (E4XTREM)

2025-12-12T08:39:12Z

Elena.delaluna: /* LNF - Nationally funded project */

== LNF - Nationally funded project ==

'''Title''': '''Investigación, diseño, Estudio y Ensayo de componentes sometidos a Entornos EXtremos para validación industrial de Tecnologías de Envolturas REgeneradoras asociadas al desarrollo de REactores de fusión Magnética (E4XTREM)'''

'''Reference''': PLEC2024-011136 (Transmisiones) & MIG-20242101 (CDTI)

'''Programme and date''': Programa de Transferencia y Colaboración del Plan Estatal de Investigación Científica, Técnica y de Innovación 2024-2027.

'''Programme type (Modalidad de proyecto)''': Programa “Misiones de Ciencia e Innovación - Transmisiones” del año 2024 (PLEC2024-011136)

Proyecto MIG-20242101 subvencionado por CDTI – Centro de Desarrollo Tecnológico y la Innovación

'''Area/subarea (Área temática / subárea)''':

'''Principal Investigator(s)''': [https://orcid.org/0000-0001-8725-8167 Iole Palermo]

'''Project type''': Proyecto coordinado

'''Start-end dates''': dd/mm/yyyy - dd/mm/yyyy

'''Financing granted (direct costs)''': 0 €

{| class="wikitable"
! Proyecto PLEC2024-011136 financiado por MICIU /AEI /10.13039/501100011033/ FEDER, UE !! Proyecto MIG-20242101 subvencionado por CDTI – Centro de Desarrollo Tecnológico y la Innovación
|-
| [[File:LogoOficial_PlanNacional_2021.png|500px]]
| [[File:CDTI_Logo.png|500px]]
|}

== Description of the project ==

The [https://projects.ciemat.es/es/web/e4xtrem/inicio E4XTREM project] falls under Thematic Priority 1 established in the TRANSMISIONES 2024 Programme: “Boosting the development of a Spanish fusion industry: advancing technologies that pave the way toward fusion.”

The project focuses primarily on Breeding Blanket technologies and on the development of auxiliary facilities with advanced testing capabilities, enabling Spanish industry to contribute high-value innovation to the development of fusion devices.

E4XTREM addresses novel, high-impact challenges. Its key ideas and primary objectives include:

*Construction of a pilot facility capable of hosting prototypes of various kinds: FASTER (Facility to Support Tritium Breeding Technology Experimental Research). This installation will enable the testing and functional validation of critical systems and components for future fusion reactors (from TRL0 to TRL4).
*Design of an irradiation module for IFMIF-DONES to test Breeding Blanket technologies (TRL2 to TRL3).
*Construction of a simplified prototype (test module) of a breeding system (BB/TBM type or irradiation module) to be tested in FASTER (TRL0 to TRL4).
*Development of new coatings for fusion environments (TRL3 to TRL4).

== Project documentation ==

(Optional) Add the project proposal and the final report at the end of the project, and any other information related with the project

== Main results ==

Enter text here (summary of main project results from the final report)

== Dissemination of project results (peer-reviewed publications and conference presentations) ==



== References ==
<references />


<hr>
[[LNF:Nationally Funded Projects|Back to list of nationally funded projects]]

[[Category:LNF Nationally Funded Projects]]

LNF: Investigación, diseño, Estudio y Ensayo de componentes sometidos a Entornos EXtremos para validación industrial de Tecnologías de Envolturas REgeneradoras asociadas al desarrollo de REactores de fusión Magnética (E4XTREM)

2025-12-12T08:34:36Z

Elena.delaluna: /* LNF - Nationally funded project */

== LNF - Nationally funded project ==

'''Title''': '''Investigación, diseño, Estudio y Ensayo de componentes sometidos a Entornos EXtremos para validación industrial de Tecnologías de Envolturas REgeneradoras asociadas al desarrollo de REactores de fusión Magnética (E4XTREM)'''

'''Reference''': PLEC2024-011136 (Transmisiones) & MIG-20242101 (CDTI)

'''Programme and date''': Programa de Transferencia y Colaboración del Plan Estatal de Investigación Científica, Técnica y de Innovación 2024-2027.

'''Programme type (Modalidad de proyecto)''': Programa “Misiones de Ciencia e Innovación - Transmisiones” del año 2024 (PLEC2024-011136)

Proyecto MIG-20242101 subvencionado por CDTI – Centro de Desarrollo Tecnológico y la Innovación

'''Area/subarea (Área temática / subárea)''':

'''Principal Investigator(s)''': [https://orcid.org/0000-0001-8725-8167 Iole Palermo]

'''Project type''': Proyecto coordinado

'''Start-end dates''': dd/mm/yyyy - dd/mm/yyyy

'''Financing granted (direct costs)''': 0 €

'''Acknowledgement''': Proyecto PLEC2024-011136 - financiado por MICIU /AEI /10.13039/501100011033/ FEDER, UE

[[File:LogoOficial_PlanNacional_2021.png|500px]]

[[File:CDTI_Logo.png|500px]]

== Description of the project ==

The [https://projects.ciemat.es/es/web/e4xtrem/inicio E4XTREM project] falls under Thematic Priority 1 established in the TRANSMISIONES 2024 Programme: “Boosting the development of a Spanish fusion industry: advancing technologies that pave the way toward fusion.”

The project focuses primarily on Breeding Blanket technologies and on the development of auxiliary facilities with advanced testing capabilities, enabling Spanish industry to contribute high-value innovation to the development of fusion devices.

E4XTREM addresses novel, high-impact challenges. Its key ideas and primary objectives include:

*Construction of a pilot facility capable of hosting prototypes of various kinds: FASTER (Facility to Support Tritium Breeding Technology Experimental Research). This installation will enable the testing and functional validation of critical systems and components for future fusion reactors (from TRL0 to TRL4).
*Design of an irradiation module for IFMIF-DONES to test Breeding Blanket technologies (TRL2 to TRL3).
*Construction of a simplified prototype (test module) of a breeding system (BB/TBM type or irradiation module) to be tested in FASTER (TRL0 to TRL4).
*Development of new coatings for fusion environments (TRL3 to TRL4).

== Project documentation ==

(Optional) Add the project proposal and the final report at the end of the project, and any other information related with the project

== Main results ==

Enter text here (summary of main project results from the final report)

== Dissemination of project results (peer-reviewed publications and conference presentations) ==



== References ==
<references />


<hr>
[[LNF:Nationally Funded Projects|Back to list of nationally funded projects]]

[[Category:LNF Nationally Funded Projects]]

File:CDTI Logo.png

2025-12-12T08:30:56Z

Elena.delaluna:

LNF: Investigación, diseño, Estudio y Ensayo de componentes sometidos a Entornos EXtremos para validación industrial de Tecnologías de Envolturas REgeneradoras asociadas al desarrollo de REactores de fusión Magnética (E4XTREM)

2025-12-12T08:24:13Z

Elena.delaluna: /* Description of the project */

== LNF - Nationally funded project ==

'''Title''': '''Investigación, diseño, Estudio y Ensayo de componentes sometidos a Entornos EXtremos para validación industrial de Tecnologías de Envolturas REgeneradoras asociadas al desarrollo de REactores de fusión Magnética (E4XTREM)'''

'''Reference''': PLEC2024-011136

'''Programme and date''': Programa de Transferencia y Colaboración del Plan Estatal de Investigación Científica, Técnica y de Innovación 2024-2027.

'''Programme type (Modalidad de proyecto)''': Programa “Misiones de Ciencia e Innovación - Transmisiones” del año 2024

'''Area/subarea (Área temática / subárea)''':

'''Principal Investigator(s)''': [https://orcid.org/0000-0001-8725-8167 Iole Palermo]

'''Project type''': Proyecto coordinado

'''Start-end dates''': dd/mm/yyyy - dd/mm/yyyy

'''Financing granted (direct costs)''': 0 €

'''Acknowledgement''': Proyecto PLEC2024-011136 - financiado por MICIU /AEI /10.13039/501100011033/ FEDER, UE

[[File:LogoOficial_PlanNacional_2021.png|500px]]

== Description of the project ==

The [https://projects.ciemat.es/es/web/e4xtrem/inicio E4XTREM project] falls under Thematic Priority 1 established in the TRANSMISIONES 2024 Programme: “Boosting the development of a Spanish fusion industry: advancing technologies that pave the way toward fusion.”

The project focuses primarily on Breeding Blanket technologies and on the development of auxiliary facilities with advanced testing capabilities, enabling Spanish industry to contribute high-value innovation to the development of fusion devices.

E4XTREM addresses novel, high-impact challenges. Its key ideas and primary objectives include:

*Construction of a pilot facility capable of hosting prototypes of various kinds: FASTER (Facility to Support Tritium Breeding Technology Experimental Research). This installation will enable the testing and functional validation of critical systems and components for future fusion reactors (from TRL0 to TRL4).
*Design of an irradiation module for IFMIF-DONES to test Breeding Blanket technologies (TRL2 to TRL3).
*Construction of a simplified prototype (test module) of a breeding system (BB/TBM type or irradiation module) to be tested in FASTER (TRL0 to TRL4).
*Development of new coatings for fusion environments (TRL3 to TRL4).

== Project documentation ==

(Optional) Add the project proposal and the final report at the end of the project, and any other information related with the project

== Main results ==

Enter text here (summary of main project results from the final report)

== Dissemination of project results (peer-reviewed publications and conference presentations) ==



== References ==
<references />


<hr>
[[LNF:Nationally Funded Projects|Back to list of nationally funded projects]]

[[Category:LNF Nationally Funded Projects]]

LNF: Investigación, diseño, Estudio y Ensayo de componentes sometidos a Entornos EXtremos para validación industrial de Tecnologías de Envolturas REgeneradoras asociadas al desarrollo de REactores de fusión Magnética (E4XTREM)

2025-12-12T08:23:49Z

Elena.delaluna: /* References */

== LNF - Nationally funded project ==

'''Title''': '''Investigación, diseño, Estudio y Ensayo de componentes sometidos a Entornos EXtremos para validación industrial de Tecnologías de Envolturas REgeneradoras asociadas al desarrollo de REactores de fusión Magnética (E4XTREM)'''

'''Reference''': PLEC2024-011136

'''Programme and date''': Programa de Transferencia y Colaboración del Plan Estatal de Investigación Científica, Técnica y de Innovación 2024-2027.

'''Programme type (Modalidad de proyecto)''': Programa “Misiones de Ciencia e Innovación - Transmisiones” del año 2024

'''Area/subarea (Área temática / subárea)''':

'''Principal Investigator(s)''': [https://orcid.org/0000-0001-8725-8167 Iole Palermo]

'''Project type''': Proyecto coordinado

'''Start-end dates''': dd/mm/yyyy - dd/mm/yyyy

'''Financing granted (direct costs)''': 0 €

'''Acknowledgement''': Proyecto PLEC2024-011136 - financiado por MICIU /AEI /10.13039/501100011033/ FEDER, UE

[[File:LogoOficial_PlanNacional_2021.png|500px]]

== Description of the project ==

The E4XTREM project falls under Thematic Priority 1 established in the TRANSMISIONES 2024 Programme: “Boosting the development of a Spanish fusion industry: advancing technologies that pave the way toward fusion.”

The project focuses primarily on Breeding Blanket technologies and on the development of auxiliary facilities with advanced testing capabilities, enabling Spanish industry to contribute high-value innovation to the development of fusion devices.

E4XTREM addresses novel, high-impact challenges. Its key ideas and primary objectives include:

*Construction of a pilot facility capable of hosting prototypes of various kinds: FASTER (Facility to Support Tritium Breeding Technology Experimental Research). This installation will enable the testing and functional validation of critical systems and components for future fusion reactors (from TRL0 to TRL4).
*Design of an irradiation module for IFMIF-DONES to test Breeding Blanket technologies (TRL2 to TRL3).
*Construction of a simplified prototype (test module) of a breeding system (BB/TBM type or irradiation module) to be tested in FASTER (TRL0 to TRL4).
*Development of new coatings for fusion environments (TRL3 to TRL4).

== Project documentation ==

(Optional) Add the project proposal and the final report at the end of the project, and any other information related with the project

== Main results ==

Enter text here (summary of main project results from the final report)

== Dissemination of project results (peer-reviewed publications and conference presentations) ==



== References ==
<references />


<hr>
[[LNF:Nationally Funded Projects|Back to list of nationally funded projects]]

[[Category:LNF Nationally Funded Projects]]

LNF: Investigación, diseño, Estudio y Ensayo de componentes sometidos a Entornos EXtremos para validación industrial de Tecnologías de Envolturas REgeneradoras asociadas al desarrollo de REactores de fusión Magnética (E4XTREM)

2025-12-12T08:23:20Z

Elena.delaluna: /* LNF - Nationally funded project */

== LNF - Nationally funded project ==

'''Title''': '''Investigación, diseño, Estudio y Ensayo de componentes sometidos a Entornos EXtremos para validación industrial de Tecnologías de Envolturas REgeneradoras asociadas al desarrollo de REactores de fusión Magnética (E4XTREM)'''

'''Reference''': PLEC2024-011136

'''Programme and date''': Programa de Transferencia y Colaboración del Plan Estatal de Investigación Científica, Técnica y de Innovación 2024-2027.

'''Programme type (Modalidad de proyecto)''': Programa “Misiones de Ciencia e Innovación - Transmisiones” del año 2024

'''Area/subarea (Área temática / subárea)''':

'''Principal Investigator(s)''': [https://orcid.org/0000-0001-8725-8167 Iole Palermo]

'''Project type''': Proyecto coordinado

'''Start-end dates''': dd/mm/yyyy - dd/mm/yyyy

'''Financing granted (direct costs)''': 0 €

'''Acknowledgement''': Proyecto PLEC2024-011136 - financiado por MICIU /AEI /10.13039/501100011033/ FEDER, UE

[[File:LogoOficial_PlanNacional_2021.png|500px]]

== Description of the project ==

The E4XTREM project falls under Thematic Priority 1 established in the TRANSMISIONES 2024 Programme: “Boosting the development of a Spanish fusion industry: advancing technologies that pave the way toward fusion.”

The project focuses primarily on Breeding Blanket technologies and on the development of auxiliary facilities with advanced testing capabilities, enabling Spanish industry to contribute high-value innovation to the development of fusion devices.

E4XTREM addresses novel, high-impact challenges. Its key ideas and primary objectives include:

*Construction of a pilot facility capable of hosting prototypes of various kinds: FASTER (Facility to Support Tritium Breeding Technology Experimental Research). This installation will enable the testing and functional validation of critical systems and components for future fusion reactors (from TRL0 to TRL4).
*Design of an irradiation module for IFMIF-DONES to test Breeding Blanket technologies (TRL2 to TRL3).
*Construction of a simplified prototype (test module) of a breeding system (BB/TBM type or irradiation module) to be tested in FASTER (TRL0 to TRL4).
*Development of new coatings for fusion environments (TRL3 to TRL4).

== Project documentation ==

(Optional) Add the project proposal and the final report at the end of the project, and any other information related with the project

== Main results ==

Enter text here (summary of main project results from the final report)

== Dissemination of project results (peer-reviewed publications and conference presentations) ==



== References ==
<references />

''' DO NOT FORGET TO ADD THE CORRESPONDING LOGO AT THE BOTTOM OF THE PAGE (see the link provided in the main page)'''


<hr>
[[LNF:Nationally Funded Projects|Back to list of nationally funded projects]]

[[Category:LNF Nationally Funded Projects]]

LNF: Investigación, diseño, Estudio y Ensayo de componentes sometidos a Entornos EXtremos para validación industrial de Tecnologías de Envolturas REgeneradoras asociadas al desarrollo de REactores de fusión Magnética (E4XTREM)

2025-12-12T08:22:28Z

Elena.delaluna: /* LNF - Nationally funded project */

== LNF - Nationally funded project ==

'''Title''': '''Investigación, diseño, Estudio y Ensayo de componentes sometidos a Entornos EXtremos para validación industrial de Tecnologías de Envolturas REgeneradoras asociadas al desarrollo de REactores de fusión Magnética (E4XTREM)'''

'''Reference''': PLEC2024-011136

'''Programme and date''': Programa de Transferencia y Colaboración del Plan Estatal de Investigación Científica, Técnica y de Innovación 2024-2027.

'''Programme type (Modalidad de proyecto)''': Programa “Misiones de Ciencia e Innovación - Transmisiones” del año 2024

'''Area/subarea (Área temática / subárea)''':

'''Principal Investigator(s)''': [https://orcid.org/0000-0000-0000-0000 John Doe]

'''Project type''': Proyecto coordinado

'''Start-end dates''': dd/mm/yyyy - dd/mm/yyyy

'''Financing granted (direct costs)''': 0 €

'''Acknowledgement''': Proyecto PLEC2024-011136 - financiado por MICIU /AEI /10.13039/501100011033/ FEDER, UE

[[File:LogoOficial_PlanNacional_2021.png|500px]]

== Description of the project ==

The E4XTREM project falls under Thematic Priority 1 established in the TRANSMISIONES 2024 Programme: “Boosting the development of a Spanish fusion industry: advancing technologies that pave the way toward fusion.”

The project focuses primarily on Breeding Blanket technologies and on the development of auxiliary facilities with advanced testing capabilities, enabling Spanish industry to contribute high-value innovation to the development of fusion devices.

E4XTREM addresses novel, high-impact challenges. Its key ideas and primary objectives include:

*Construction of a pilot facility capable of hosting prototypes of various kinds: FASTER (Facility to Support Tritium Breeding Technology Experimental Research). This installation will enable the testing and functional validation of critical systems and components for future fusion reactors (from TRL0 to TRL4).
*Design of an irradiation module for IFMIF-DONES to test Breeding Blanket technologies (TRL2 to TRL3).
*Construction of a simplified prototype (test module) of a breeding system (BB/TBM type or irradiation module) to be tested in FASTER (TRL0 to TRL4).
*Development of new coatings for fusion environments (TRL3 to TRL4).

== Project documentation ==

(Optional) Add the project proposal and the final report at the end of the project, and any other information related with the project

== Main results ==

Enter text here (summary of main project results from the final report)

== Dissemination of project results (peer-reviewed publications and conference presentations) ==



== References ==
<references />

''' DO NOT FORGET TO ADD THE CORRESPONDING LOGO AT THE BOTTOM OF THE PAGE (see the link provided in the main page)'''


<hr>
[[LNF:Nationally Funded Projects|Back to list of nationally funded projects]]

[[Category:LNF Nationally Funded Projects]]

LNF: Investigación, diseño, Estudio y Ensayo de componentes sometidos a Entornos EXtremos para validación industrial de Tecnologías de Envolturas REgeneradoras asociadas al desarrollo de REactores de fusión Magnética (E4XTREM)

2025-12-12T08:21:44Z

Elena.delaluna: Created page with "== LNF - Nationally funded project == '''Title''': '''Investigación, diseño, Estudio y Ensayo de componentes sometidos a Entornos EXtremos para validación industrial de Tecnologías de Envolturas REgeneradoras asociadas al desarrollo de REactores de fusión Magnética (E4XTREM)''' '''Reference''': Referencia Plan Nacional '''Programme and date''': Programa de Transferencia y Colaboración del Plan Estatal de Investigación Científica, Técnica y de Innovación 202..."

== LNF - Nationally funded project ==

'''Title''': '''Investigación, diseño, Estudio y Ensayo de componentes sometidos a Entornos EXtremos para validación industrial de Tecnologías de Envolturas REgeneradoras asociadas al desarrollo de REactores de fusión Magnética (E4XTREM)'''

'''Reference''': Referencia Plan Nacional

'''Programme and date''': Programa de Transferencia y Colaboración del Plan Estatal de Investigación Científica, Técnica y de Innovación 2024-2027.

'''Programme type (Modalidad de proyecto)''': Programa “Misiones de Ciencia e Innovación - Transmisiones” del año 2024

'''Area/subarea (Área temática / subárea)''':

'''Principal Investigator(s)''': [https://orcid.org/0000-0000-0000-0000 John Doe]

'''Project type''': Proyecto coordinado

'''Start-end dates''': dd/mm/yyyy - dd/mm/yyyy

'''Financing granted (direct costs)''': 0 €

'''Acknowledgement''': Proyecto PLEC2024-011136 - financiado por MICIU /AEI /10.13039/501100011033/ FEDER, UE

[[File:LogoOficial_PlanNacional_2021.png|500px]]

== Description of the project ==

The E4XTREM project falls under Thematic Priority 1 established in the TRANSMISIONES 2024 Programme: “Boosting the development of a Spanish fusion industry: advancing technologies that pave the way toward fusion.”

The project focuses primarily on Breeding Blanket technologies and on the development of auxiliary facilities with advanced testing capabilities, enabling Spanish industry to contribute high-value innovation to the development of fusion devices.

E4XTREM addresses novel, high-impact challenges. Its key ideas and primary objectives include:

*Construction of a pilot facility capable of hosting prototypes of various kinds: FASTER (Facility to Support Tritium Breeding Technology Experimental Research). This installation will enable the testing and functional validation of critical systems and components for future fusion reactors (from TRL0 to TRL4).
*Design of an irradiation module for IFMIF-DONES to test Breeding Blanket technologies (TRL2 to TRL3).
*Construction of a simplified prototype (test module) of a breeding system (BB/TBM type or irradiation module) to be tested in FASTER (TRL0 to TRL4).
*Development of new coatings for fusion environments (TRL3 to TRL4).

== Project documentation ==

(Optional) Add the project proposal and the final report at the end of the project, and any other information related with the project

== Main results ==

Enter text here (summary of main project results from the final report)

== Dissemination of project results (peer-reviewed publications and conference presentations) ==



== References ==
<references />

''' DO NOT FORGET TO ADD THE CORRESPONDING LOGO AT THE BOTTOM OF THE PAGE (see the link provided in the main page)'''


<hr>
[[LNF:Nationally Funded Projects|Back to list of nationally funded projects]]

[[Category:LNF Nationally Funded Projects]]

LNF:Nationally Funded Projects

2025-12-10T17:33:47Z

Elena.delaluna: /* Instructions to add a new project to the list */

Nationally funded projects of the [[Laboratorio Nacional de Fusión]].

== LNF - Nationally funded projects ==

<categorytree mode="pages">LNF Nationally Funded Projects - finished</categorytree>

<categorytree mode="pages">LNF Nationally Funded Projects</categorytree>

<div align="center">
{|
|class="wikipage" style="border:3px solid #3f63af"|
{|
! <p style="margin:3px; font-size:120%; font-weight:bold; text-align:center; padding:0.2em 0.4em">
[https://www.aei.gob.es/sites/default/files/inline-files/20250331_Guia%20comunicacion%20publicidad%20ayudas_v01.pdf Instrucciones relativas a los requisitos de publicidad en proyectos de los planes nacionales (Marzo/2025)] </p>
|}
|}
</div>

== Instructions to add a new project to the list ==

''Please read the following brief instructions''
# Log in to the FusionWiki. If you don't have an account, request one by clicking 'Create account' in the left-hand menu.
# <font color="#FF0000">''Type the name of your project page in the field below''</font>. The required format is: 'LNF:Title of my project' (without the apostrophes) (Star-End year). Note the 'LNF:' at the beginning!
# Click 'Create new project page'. Your project page will be created. Edit and save (please use 'Show preview' before saving the final version).
# Use the template provided to provide the project information
# The page can be written in English or Spanish
# The page must include at the top of the page the logo and the text for the acknowledgement associated with the type of project/year (see the link above)

<inputbox>
type=create
placeholder=LNF:Title of my project
buttonlabel=Create new project page with this title
preload=LNF:Project_template
</inputbox>

Once you save the new project page, it will automatically be included in the list above ('''provided''' you don't delete the relevant lines at the end of your project page).

LNF:Nationally Funded Projects

2025-12-10T17:33:22Z

Elena.delaluna: /* Instructions to add a new project to the list */

Nationally funded projects of the [[Laboratorio Nacional de Fusión]].

== LNF - Nationally funded projects ==

<categorytree mode="pages">LNF Nationally Funded Projects - finished</categorytree>

<categorytree mode="pages">LNF Nationally Funded Projects</categorytree>

<div align="center">
{|
|class="wikipage" style="border:3px solid #3f63af"|
{|
! <p style="margin:3px; font-size:120%; font-weight:bold; text-align:center; padding:0.2em 0.4em">
[https://www.aei.gob.es/sites/default/files/inline-files/20250331_Guia%20comunicacion%20publicidad%20ayudas_v01.pdf Instrucciones relativas a los requisitos de publicidad en proyectos de los planes nacionales (Marzo/2025)] </p>
|}
|}
</div>

== Instructions to add a new project to the list ==

''Please read the following brief instructions''
# Log in to the FusionWiki. If you don't have an account, request one by clicking 'Create account' in the left-hand menu.
# <font color="#FF0000">''Type the name of your project page in the field below''</font>. The required format is: 'LNF:Title of my project' (without the apostrophes) (Star-End year). Note the 'LNF:' at the beginning!
# Click 'Create new project page'. Your project page will be created. Edit and save (please use 'Show preview' before saving the final version).
# Use the template provided to provide the project information
# The page can be written in English or Spanish
# The page must include at the top of the page the logo and the acknowledgements associated with the type of project/year (see the link above)

<inputbox>
type=create
placeholder=LNF:Title of my project
buttonlabel=Create new project page with this title
preload=LNF:Project_template
</inputbox>

Once you save the new project page, it will automatically be included in the list above ('''provided''' you don't delete the relevant lines at the end of your project page).

LNF: (2018-2021) Pedestal studies in high confinement regimes in tokamaks in ITER relevant conditions (HMODPEDTOK)

2025-12-10T17:17:03Z

Elena.delaluna: /* LNF - Nationally funded project */

== LNF - Nationally funded project ==

'''Title''': Pedestal studies in high confinement regimes in tokamaks in ITER relevant conditions (HMODPEDTOK)

'''Reference''': FIS2017-85252-R

'''Programme and date''': CONVOCATORIA 2017 PROYECTOS DE I+D+i, DEL PROGRAMA ESTATAL DE INVESTIGACION, DESARROLLO E INNOVACION ORIENTADA A LOS RETOS DE LA SOCIEDAD

'''Programme type (Modalidad de proyecto)''': I+D RETOS 2017

'''Area/subarea (Área temática / subárea)''': Energía / Fusión Termonuclear

'''Principal Investigator(s)''': [https://orcid.org/0000-0002-5420-0126 Elena de la Luna] and [http://orcid.org/0000-0002-4815-3407 Emilia R. Solano]

'''Project type''': Proyecto individual

'''Start-end dates''': 01/01/2018 - 31/12/2020 (extended to 30/09/2021)

'''Financing granted (direct costs)''': 72.600 €

[[File:Logo_proyectos_PN_2018.png|500px]]

== Descripción del proyecto ==

Esta propuesta se enmarca dentro del programa de fusión europeo y tiene como objetivo contribuir a mejorar la predicción de los regímenes de operación que se esperan en los futuros dispositivos de fusión como ITER. El proyecto se centra en tres aspectos fundamentales de la operación de ITER relacionados con la física del pedestal: la transición L-H, el control de impurezas mediante el control activo de los ELMs y regímenes de confinamiento sin ELMs.

# Para la transición L-H se plantean estudios teóricos y experimentales. Hemos propuesto un modelo innovador para la transición L-H basado en la criticidad y los estados de magnetización del plasma. Es nuestra intención continuar con el desarrollo de este modelo y validar los resultados obtenidos mediante simulaciones del transporte de partículas y calor y comparaciones con la teoría de superconductividad. Experimentalmente, nuestra propuesta se enfoca en el estudio de la actividad MHD asociada a la transición L-H. Hemos identificado en JET una oscilación magnética y coherente de modo toroidal n=0 que aparece cerca de la transición L-H y que se ha denominado modo M. Este modo coherente puede desvanecerse lentamente hasta convertirse en ELMs pequeños (tipo III) o permanecer de forma estacionaria hasta que la potencia de calentamiento o la densidad aumente. Nuestro objetivo es caracterizar este modo y desarrollar un modelo teórico basado en las observaciones experimentales de las que disponemos.
# En el área del control de impurezas, nuestra propuesta se centra en la aplicación de métodos que permiten el aumento controlado de la frecuencia de los ELMs para minimizar el contenido de impurezas en el plasma. En particular, estudiaremos los llamados vertical kicks, que son desplazamientos verticales muy rápidos del plasma, y la inyección de pellets. El control de impurezas es esencial en la operación de tokamaks con tungsteno (W) presente en las paredes del dispositivo. El aumento del contenido de impurezas en el plasma puede dar lugar a una pérdida de confinamiento y al colapso radiativo del plasma. Nuestros objetivos en este proyecto son: a) evaluar la capacidad de los métodos activos de generación de ELMs para el control de impurezas en JET y b) validar y desarrollar los modelos de transporte necesarios para así poder extrapolar los resultados obtenidos a ITER. Los estudios se enfocarán en regímenes de operación relevantes para ITER, como son el acceso a modo H en la fase inicial de la subida de la corriente del plasma, durante la fase de corriente constante en situaciones de baja potencia de calentamiento y la transición H-L durante la fase de bajada de la corriente.
# El modo QH (Quiescent H-mode) es un régimen de alto confinamiento con gradientes elevados en el borde del plasma pero sin ELMs. En este régimen, la aparición en el borde del plasma de un modo MHD conocido como Edge Harmonic Oscillation (EHO) genera suficiente transporte en la región del pedestal como para evitar la acumulación de impurezas incluso en ausencia de ELMs. Nosotros especulamos que el llamado Outer mode (OM) que se observa en JET es, de hecho, un modo tipo EHO. Nuestro objetivo es comprobar si esta hipótesis es correcta comparando datos y llevaremos a cabo simulaciones no-lineales de la actividad MHD en DIII-D y posiblemente en JET. A la larga, si demostramos que EHO y Outer Mode son el mismo fenómeno, estaremos en mejores condiciones para la aplicabilidad del QH-mode a ITER.

== Resumen de los resultados más importantes del proyecto ==

Las tareas de investigación de este proyecto se enmarcan en el programa de fusión europeo y tienen como objetivo contribuir a mejorar la predicción de los regímenes de operación que se esperan en los futuros dispositivos de fusión como ITER y DEMO. El proyecto se centra en tres aspectos fundamentales: la transición del modo de bajo (modo L) a alto (modo H) confinamiento, el control de impurezas mediante el control activo de los ELMs (del inglés Edge Localized Modes) y regímenes de confinamiento sin ELMs o con ELMs de pequeño tamaño (para ITER y DEMO).

Los experimentos realizados en JET para investigar de qué depende la potencia de calentamiento umbral para acceder al modo H (PLH) han permitido construir una extensa base de datos, que incluye plasmas de hidrógeno, deuterio (D), tritio (T), deuterio-tritio (la mezcla que se utilizará en futuros reactores de fusión) y helio. Los datos de tritio y DT son únicos en el mundo. Los experimentos han permitido documentar cómo varía el valor de la densidad que minimiza el umbral de potencia de la transición L-H (n<sub>e,min</sub>) en función de la composición del plasma. En los plasmas de tritio n<sub>e,min</sub> es un 25% más baja que en deuterio, y en helio es el doble que en deuterio. El dato en Helio tiene implicaciones para la operación inicial en ITER. Medidas por reflectometría Doppler del campo eléctrico en el borde del plasma muestran que este no varía a lo largo de la rampa de potencia previa de la transición, un dato que apoya teorías de transición de fase magnéticas frente a las convencionales basadas en la cizalladura del campo eléctrico.
Es de resaltar que las campañas experimentales de tritio y deuterio-tritio en JET han producido numerosos resultados que se seguirán analizando. Se espera profundizar en los resultados mencionados, estudiando la influencia de la composición del plasma en los perfiles de densidad, temperatura y presión previos de la transición L-H. Estos datos han permitido empezar a desarrollar nuevas leyes de escala para JET y tokamaks con paredes metálicas. La nueva base de datos de transición L-H permitirá perfeccionar y comprender estas leyes de escala y asi mejorar las predicciones para ITER.

En el área del control de impurezas, nos hemos centrado en evaluar el impacto de métodos activos de control de ELMs (inyección de gas, ‘kicks’ y pellets) en la fase de salida del modo H, donde se produce la bajada de la corriente del plasma y tiene lugar la transición H-L provocada por la reducción de la potencia de calentamiento. Esta es una fase particularmente complicada para ITER puesto que durante esta fase es necesario retrasar en lo posible la transición H-L y así evitar una transición brusca a modo L que, de producirse cuando el contenido en energía del plasma es todavía elevado, podría llegar a comprometer el control de la posición radial del plasma y poner en peligro la integridad de la pared del tokamak. Este trabajo ha demostrado que el control de ELMs, en particular el uso de ‘kicks’ y pellets, juega un papel crucial durante esta fase, contribuyendo a retrasar la transición H-L y evitando así la acumulación de impurezas en el centro del plasma y las disrupciones que esto provoca. La reducción del número de disrupciones es uno de los retos a los que se enfrenta la operación en ITER, de ahí la importancia de este trabajo. Estos experimentos también han permitido validar simulaciones de transporte muy detalladas, lo que permite tener una mayor confianza en las predicciones de esta fase de la descarga durante la operación de ITER.
También hay que mencionar que con estos experimentos hemos demostrado que los «kicks» son eficientes para aumentar la frecuencias de los ELMs no solo durante la fase estacionaria del modo H, a potencias de calentamiento muy por encima de la potencia necesaria para acceder a modo H, sino también en condiciones cercanas a la transición H-L. Estos estudios son relevantes para ITER, puesto que los ´kicks´ podrían ser el único método de control de ELMs disponible durante la primera fase de operación de ITER a baja corriente (5.3 MA/1.8 T, plasmas de He o H, que se denomina en la literatura PFPO).

En cuanto al estudio de plasmas con ELMs pequeños o sin ELMs, de gran importancia para ITER y DEMO, hemos contribuido a desarrollar el modo H “quiescent” en el tokamak AUG. Se caracterizan por una oscilación harmónica en el borde (EHO). También hemos detectado indicios del EHO en plasmas de tritio en JET. Por último, hemos investigado en JET un nuevo régimen de operación en modo H, obtenido al suprimir la inyección de gas. Este regimen presenta un buen confinamiento, con ELMs de pequeño tamaño y sin acumulación de impurezas. Se trata de un escenario novedoso en JET, especialmente porque se alcanza a baja colisionalidad en el pedestal, condición en la que se espera operen los plasmas en modo H en ITER.


== Cronograma del proyecto ==
* 17/Septiembre/2017: Solicitud enviada
* 14/Junio/2018: Resolución del BOE - proyecto aprobado, con una duración inicial de 3 años y una subvención de 72.600€. La fecha de inicio del periodo de ejecución será el 1 de enero de 2018 para todos los proyectos
* Junio/2018: [https://wiki.fusion.ciemat.es/fusionwiki/images/0/08/FIS2017-85252-R_Resolucion_concesion_proyecto.pdf Valoración proyecto] - Calificación A
* 31/Agosto/2020: [https://wiki.fusion.ciemat.es/fusionwiki/images/b/b9/FIS2017-85252-R_Concesion_de_prorroga.pdf Petición & Concesión de prórroga] - Duración inicial del proyecto: 01/01/2018 - 31/12/2020. Se solicita una prórroga de 1 año, pero solo se conceden 9 meses.
* 21/Marzo/2022: Entrega del informe final
* Julio-2023: [https://wiki.fusion.ciemat.es/fusionwiki/images/3/3f/FIS2017-85252-Valoracion_Informe_Final_Julio2023.pdf Valoración Informe final] - MUY SATISFACTORIO

== Difusión de los resultados de este proyecto ==
=== Publicaciones en revistas con “peer review” directamente relacionadas con los resultados del proyecto ===
(todos los artículos en esta lista se enviaron a publicar durante la ejecución de este proyecto)

#F. Koechl, A. Loarte, E. de la Luna, et al. ''W transport and accumulation in the terminatation phase of JET H-mode discharges and implications for ITER''. Plasma Physics and Controlled Fusion 60 (2018) 074008
#F.J. Artola, G.T.A. Huijsmans, M. Hoelzl, P. Beyer, A. Loarte and Y. Gribov. ''Non-linear magnetohydrodynamic simulations of edge localised mode triggering via vertical position oscillations in ITER'', Nuclear Fusion 58 (2018) 096018
#P.C. de Vries, T. C Luce, (…), E de la Luna, et al. ''Multimachine analysis of termination scenarios with comparison of simulations of controlled shutdown of ITER discharges''. Nuclear Fusion (2018) 026019
#J. C. Hillesheim, E. Delabie, E. R. Solano, …, E. de la Luna, et al. ''Implications of JET-ILW L-H Transition Studies for ITER''. Proc. 27th IAEA Fusion Energy Conference, Gandhinagar, India (22-27 October, 2018) EX/41 (invited)
#C Silva, JC Hillesheim, L Gil,… ER Solano, et al. ''Geodesic acoustic mode evolution in L-mode approaching the L–H transition on JET'', Plasma Physics and Controlled Fusion 61 (2019) 075007
#D.I. Réfy, E.R. Solano et al, '' Identity of the JET M-mode and the ASDEX Upgrade I-phase phenomena '', Nuclear Fusion, 60 (2020) 056004 6. E. R. Solano, …, E de la Luna, …, A. Loarte,… et al, ''L–H transition threshold studies in Helium plasmas at JET'', Nuclear Fusion 61 (2021) 124001
#C Silva, E.R. Solano, et al, ''Structure of the JET edge radial electric field in He and D plasmas'', Nuclear Fusion 61 (2021) 126006
#M. Lennholm, …. E. de la Luna, et al. ''Statistical assessment of ELM triggering by pellets on JET'', Nuclear Fusion 61 (2021) 036035
#E. de la Luna, A. Loarte, …, E. R. Solano and JET contributors. ''Evolution and control of tungsten transport in the termination phase of JET H-mode discharges and implications for ITER''. Proc. 27th IAEA Fusion Energy Conference, Gandhinagar, India (22-27 October, 2018) EX/2-1 3 (invited)
#E. R. Solano, G. Birkenmeier, …, E. de la Luna et al. '' L-H Transition Studies at JET: H, D, He and T.'' Proc. 28th IAEA Fusion Energy Conference. Virtual Event (10-15 Mayo, 2021) EX/2-3 (invited)
#E. de la Luna, M. Sertoli, J. García, … E. R. Solano, et al. ''Exploring the physics of a high-performance H-mode with small ELMs and zero gas puffing in JET-ILW''. Proc. 28th IAEA Fusion Energy Conference. Virtual Event (10-15 Mayo, 2021) EX/3-2 (invited)
#J. García, E. de la Luna, et al. ''New H-mode regimes with small ELMs and high thermal confinement in the Joint European Torus''. Physics of Plasmas 29 (2022) 032505 (Featured article)
#ER Solano, …. E. de la Luna, …., J. García, …, A. Loarte, …. , A. Manzanares, et al, ''Recent progress in LH transition studies at JET: Tritium, Helium, Hydrogen and Deuterium'', Nuclear Fusion 62 (2022) 076026

=== Asistencia a congresos, conferencias o workshops relacionados con el proyecto (miembros del equipo investigador) ===
# 45th EPS Conference on Plasma Physics (República Checa), 2018. '' Using rotating current ribbons to model MHD: the EHO ''. E.R.Solano, K. Burrel, et al. Tipo de comunicación: Póster
# 45th EPS Conference on Plasma Physics (República Checa), 2018. ''An in-depth look into the physics of ELM triggering via vertical kicks through non-linear MHD simulations''. J. Artola, G. Huijsmans, M. Hoelzl, P. Beyer, A. Loarte, Y. Gribov, E. de la Luna, F. Koechl and JET contributors. Tipo de comunicación: '''Charla invitada'''
#23rd Joint EU-US Transport Task Force Meeting (España), 2018. '' Power balance analysis at the L to H transition in JET-ILW''. E.R. Solano, et al. Tipo de comunicación: '''Charla invitada'''
#27th IAEA Fusion Energy Conference (India), 2018. '' Evolution and control of tungsten transport in the termination phase of JET H-mode discharges and implications for ITER ''. E. de la Luna, A. Loarte, F. Rimini, …, E. R. Solano et al. Tipo de comunicación:'''Charla invitada'''
#27th IAEA Fusion Energy Conference (India), 2018. ''Implications of JET-ILW L-H Transition Studies for ITER''. J. C. Hillesheim, E. Delabie, E. R. Solano, …, E. de la Luna, et al. Tipo de comunicación: '''Charla invitada'''
#27th IAEA Fusion Energy Conference (India), 2018. ''Stellarator Nonlinearly Saturated Periodicity-Breaking Ideal Magnetohydrodynamic Equilibrium States''. D. López-Bruna et al. Tipo de comunicación: Poster
#27th IAEA Fusion Energy Conference (India), 2018. ''ELM and ELM-control simulations'' SA. Pamela, N. Aiba,…, E. de la Luna, et al. Tipo de comunicación: '''Charla invitada'''
#27th IAEA Fusion Energy Conference, (India), 2018. ''QH-mode extrapolation for ITER Q=10 plasma with nonlinear MHD code JOREK''. F. Liu, G.T.A. Huijsmans, A. Loarte, M. Hoelzl, et al. Tipo de comunicación: Póster
#ITPA Edge Plasma and Pedestal Physics Topical Group (ITPA es el acrónimo de International Tokamak Physics Activities) (Francia), 2018. ''Isotope effect on L-H transition from historical T and DT campaigns at JET''. E.R. Solano. Tipo de comunicación: '''Oral'''
#ITPA Edge Plasma and Pedestal Physics Topical Group (ITPA es el acrónimo de International Tokamak Physics Activities) (Francia), 2018. ''JET L-H transition experimental plans''. E.R. Solano. Tipo de comunicación: '''Oral'''
#61st Annual Meeting of the APS Division of Plasma Physics (EEUU), 2019. ''Helium L-H transition threshold studies in JET-ILW''. E.R. Solano, E. Delabie, …, E. de la Luna, … Tipo de comunicación: '''Oral''' durante la sesión sobre ITER
#61st Annual Meeting of the APS Division of Plasma Physics (EEUU), 2019. ''Development of a QH-mode scenario on ASDEX Upgrade''. E. Viezzer, J. Hobirk, E.R. Solano, et al. Tipo de comunicación: Póster
#46th EPS Conference on Plasma Physics (Milan, Italia), 2019. ''Revisiting H, D and T studies of L-H transitions in JET''.E.R. Solano, et al. Tipo de comunicación: Póster
#46th EPS Conference on Plasma Physics (Milan, Italia), 2019. ''Ion heat channel at the L-H transition in JET-ILW''. P. Vincenzi, E. Delabie, E.R.Solano, et al. Tipo de comunicación: Póster
#22nd International Stellerator Workshop (EEUU), 2019. ''The HPI2 code as a tool to understand the underlying physics of cryogenic pellet injection in the stellarators TJ-II, Heliotron-J and W7-X''. N. Panadero, et al. Tipo de comunicación: Póster
#ITPA Edge Plasma and Pedestal Physics Topical Group (ITPA es el acrónimo de International Tokamak Physics Activities) (Cadarache, Francia), 2020 '' Report on the use of vertical kicks for impurity control in JET''. E. de la Luna. Tipo de comunicación: '''Oral'''
#5th Asia-Pacific Conference on Plasma Physics, 2021. ''JET L-H transition studies: overview and relevant results towards ITER operation''. P. Vincenzi, E. R. Solano, et al. Tipo de comunicación: '''Charla invitada (plenaria)'''
#47th EPS Conference on Plasma Physics (España), 2021. ''JET L-H transitions in Helium''. E.R. Solano, … E. de la Luna,…, A. Loarte, et al. Tipo de comunicación: '''Charla invitada'''
#47th EPS Conference on Plasma Physics (España), 2021. ''Progress towards a quiescent, high confinement regime for the all-metal ASDEX Upgrade tokamak''.E. Viezzer, J. Hobirk, P. Cano-Megias, E.R. Solano, et al. Tipo de comunicación: Póster
#19th European Fusion Theory Conference (evento virtual), 2021. ''L-H transition studies at JET: challenges to theory''. E. R. Solano, …, E. de la Luna, …, A. Manzanares, et al. Tipo de comunicación: '''Oral'''
#28th IAEA Fusion Energy Conference (evento virtual), 2021. ''L-H Transition Studies at JET: H, D, He and T''. E. R. Solano, G. Birkenmeier, …, E. de la Luna et al. Tipo de comunicación: '''Charla invitada'''
#28th IAEA Fusion Energy Conference (evento virtual), 2021. ''Exploring the physics of a high-performance H-mode with small ELMs and zero gas puffing in JET-ILW''. E. de la Luna, M. Sertoli, J. García, … E. R. Solano, et al. Tipo de comunicación: '''Charla invitada'''
#Edge Plasma and Pedestal Physics Topical Group (conocido como PEP), dentro de la ITPA (International Tokamak Physics Activities) (evento virtual), 2021. ''High-performance H-mode plasmas with small ELMs in JET-ILW''. E. de la Luna. Tipo de comunicación: '''Oral'''
#Edge Plasma and Pedestal Physics Topical Group (conocido como PEP), dentro de la ITPA (International Tokamak Physics Activities) (evento virtual), 2021. ''JET L-H transitions in He, D, T''. E.R. Solano. Tipo de comunicación: '''Oral'''

<hr>
[[LNF:Nationally Funded Projects|Back to list of nationally funded projects]]

[[Category:LNF Nationally Funded Projects - finished]]

2025-12-10T10:21:40Z

Elena.delaluna: /* References */

== LNF - Nationally funded project ==

'''Title''': '''Fuelling and Impurity Control Studies in the stellarators TJ-II and W7-X using Cryogenic Pellets and Tracer-Encapsulated Solid Pellets (TESPEL)'''

'''Reference''': PID2020-116599RB-I00

'''Funding Umbrella''': Plan Estatal de Investigación Científica y Técnica y de Innovación 2021-2023

'''Funding Programme''': Proyecto de investigación subvencionado por el Ministerio de Ciencia e Innovación

'''Subprogramme''': Proyectos de I+D+i Retos Investigación

'''Programme and date''': Proyectos I+D+i 2020

'''Programme type/ Modalidad''':

'''Area/subarea''': Physical Sciences / Physics and its applications

'''Principal Investigator(s)''': [https://orcid.org/0000-0002-5881-1442 Kieran Joseph McCarthy] [https://orcid.org/0000-0002-5223-391X María Isabel García Cortés]

'''Project type''': Investigación Orientada Tipo B

'''Start-end dates''': 01/09/2021 - 31/08/2025

'''Financing granted (direct costs)''': 130.000 €

== Description of the project ==

The goal of this project, which falls within the realm of magnetic confinement nuclear fusion, is to continue research initiated in projects ENE2013-48679-R and FIS2017-89326-R on fuelling and impurity control in plasmas created in the stellarators TJ-II (Ciemat, Madrid) and W7-X (Greifswald, Germany). Further research to resolve these issues is critical to demonstrate steady-state operation of helical-type fusion reactors, in particular to identify operational scenarios that ensure adequate plasma fuelling and avoidance of impurity accumulation. This project will contribute to the development and scientific exploitation of stellarators, a priority highlighted in the document "Fusion Electricity: a roadmap to the realization of fusion energy" (EFDA 2012).

1. The first aim is to investigate aspects of plasma fuelling that are still not fully understood and the effects of fuel pellets on plasma magnetic activity, plasma turbulence and plasma performance. For this, the medium-sized heliac TJ-II will be used. It is equipped with a cryogenic pellet injector (PI) for producing solid hydrogen pellets that can be injected at high velocity into the plasma. It is intended to investigate pellet fuelling as a means to enhance plasma confinement (higher stored energy, longer particle confinement) and to identify and explore new pellet phenomena. While TJ-II is equipped with a large number of modern diagnostics, it is proposed to develop a new system to measure pellet cloud density and temperature to extend knowledge of pellet physics.

2. The second aim is to continue to support impurity transport and accumulation studies in TJ-II and W7-X. Under the umbrella of a trilateral collaboration (2020-2029) with the National Institute for Fusion Science (Japan) and IPP-Max-Planck (Greifswald, Germany), Tracer-Encapsulated Solid Pellet (TESPEL) injections systems are now operated on both TJ-II and W7-X. TESPELs are polystyrene spheres (diameter <1 mm) loaded with impurity tracers (atomic elements other than fuel). This allows delivering a precise quantify of tracer to a preselected location in the plasma core, after which its transport and confinement can be studied. An important aspect of the collaboration has been the establishment of a laboratory to fabricate TESPELs at Ciemat for both devices (project FIS2017- 89326-R). Key parts of this current project are to continue TESPEL fabrication for TJ-II and W7-X at this laboratory, thereby allowing Ciemat to maintain this fruitful collaboration, and to upgrade a vacuum ultraviolet spectrometer on TJ-II to provide important spectral line data for impurity identification in W7-X.

The PI and TESPEL systems on TJ-II share a common injection guide lines. This unique set-up allows direct comparative studies of ablation, deposition and plasma response to be made thereby facilitating the understanding of common physics. Given that fuelling and impurity control are critical issues for stellarator steady-state operation, the project will allow us to continue to contribute to, and participate in, research programmes on W7-X, the stellarator of reference. Finally, team members have significant experience in the formation of young researchers at Master and PhD levels and in disseminating research to second level students and to the general public. A PhD student will undertake research in these areas during the project.

== Main Results ==

1. A pellet-induced enhanced confinement regime (or PiEC) has been identified in Neutral Beam Injection (NBI) heated discharges in TJ-II after the injection of a single cryogenic fuel pellet (H) into its plasma core <ref>1</ref>. In addition to the expected increase in core electron density, the plasma diamagnetic energy content, as determined using a diamagnetic loop, is seen to rise by up to 40%, with respect to reference discharges without pellet injection. Furthermore, the energy confinement time is significantly enhanced when compared to predictions obtained using the 2004 International Stellarator Scaling law, ISS04. Indeed, the operational regimes of other stellarator devices, such as LHD and W7-X, can be similarly extended to performance well beyond those obtainable with gas puffing alone.

2. New studies, performed with multiple pellet injections, have extended the TJ-II operational regime well beyond limits previously achieved in this device using NBI heating and gas puff<ref>2</ref>,<ref>3</ref>. In order to achieve best results, it has been determined that the plasma target electron density should to be in the range <math>1 \times 10^{19} {\mathrm m}^{-3}</math> to <math>2.5 \times 10^{19} {\mathrm m}^{-3}</math> and time separations between pellets should be close to energy confinement times, around 10 ms. It is also found, using a Charge Exchange Recombination Spectroscopy diagnostic, that while the plasma electron temperature is almost unaffected by such pellet injections, the majority ion temperature irises significantly due to reduced ion radial heat fluxes during the PiEC phase. It is also found that enhanced performance is independent of whether co- or counter-NBI heating beam is employed. Finally, record stored diamagnetic energy content and plasma beta values are achieved when the largest available pellets are employed. The results indicate that pellet injections extend the operational regime well beyond limits previously achieved in TJ-II without pellets. An important inter-machine study of cryogenic-pellet fueling in helical devices has also been made<ref>4</ref>. This was done to evaluate controlling performance bifurcations in stellarators.

3. As noted above, improved confinement associated with the injection of pellets has been observed in TJ-II during NBI phase of its plasmas. Using a simple model, the modification of turbulent transport by a pellet and how this modification affects particle confinement has been studied<ref>5</ref>. Results indicate a relationship between improved confinement and the evolution of shear flows due to turbulence, especially near low-order rational surfaces. Furthermore, experiments show that additional pellets can enhance the confinement improvement produced by the first. This effect is reproduced in the model when a second density pellet is launched soon after the first one. For this to occur, the second pellet must be injected in the transient period, before the plasma returns to steady state. In a separate, new study on enhanced confinement for a specific magnetic configuration, 100-48-65 (comparison with with and without pellets), it is found that enhanced confinement can depend strongly on plasma currents, which in turn, indicates a dependence on rotational transform (location of low-order rational surfaces in gradient region<ref>6</ref>.

4. Pellet injection experiments have been performed for a range of magnetic configurations of TJ-II in order to increase our understanding of pellet deposition profiles and of the role of rational surfaces in plasmoid drift in stellarators<ref>7</ref>. In a first instance, it is found that fast-electron impacts on a pellet can lead to ice destruction, this leading to enhanced fuelling efficiency. In a previous study, it was found that sudden pellet destruction by fast electrons inhibits the development of normal outward drifting of plasmoids that occurs when pellets are ablated by thermal electrons only. In a separate study, plasmoid drifting is found to be significantly reduced, as is observed in tokamaks, in the vicinity of rational surfaces (rational surfaces have magnetic field lines that are periodic; i.e., the magnetic field lines close back on themselves)<ref>8</ref>. This is attributed to the fact that plasmoid external charge reconnection lengths shorten when close to rational surfaces, resulting in more effective damping of plasmoid drift. Although in stellarators, the effect of plasmoid external currents on drift is expected to be negligible, compared with plasmoid internal currents, this latter effect is clearly measurable in TJ-II. In addition, code simulations reveal that enhanced drift reductions near rational surfaces lead to significantly different deposition profiles for standard magnetic configurations in TJ-II. This implies that it should be possible to identify magnetic configurations that will result in more efficient pellet fuelling. In a further study in the area, a comparison was made on the influence of plasmoid-drift mechanisms on plasma fuelling by cryogenic pellets in ITER and Wendelstein 7-X<ref>9</ref>.

5. A tracer-encapsulated solid pellet (TESPEL) system was commissioned successfully for the stellarator Wendelstein 7-X (W7-X) during its OP1.2b experimental campaign<ref>10</ref>,<ref>11</ref>,<ref>12</ref>,<ref>13</ref>. TESPELs are polystyrene encapsulated solid pellets loaded with a single tracer or multiple tracers that are employed for impurity transport studies. During the OP1.2b campaign approximately 140 pellet injections were performed with successful delivery rate of 89%, this result showing that TESPEL production is very reliable. A significant fraction of those TESPELs were fabricated at Ciemat. A large number of TESPELs have been produced at Ciemat for the 2024 and 2025 experimental campaigns on W7-X and for the 2024 campaign on the Large Helical Device (LHD) stellarator. Tracer elements used were B, C, N, O, Al, Si, Ca, Ti, Fe, Ni, Cu, Mo and W.

6. Experiments in the LHD with continuous lithium power dropping have allowed the creation of a reactor-relevant high-density plasma regime<ref>14</ref>,<ref>15</ref>. This is characterized by increased energy confinement as well as suppressed turbulence and reduced impurity confinement. The transition to this regime is driven by the continuous dropping of Li-powder grains into the plasma. When such plasmas are compared to plasmas without Li-powder the achieved high-performance characteristics include: increased plasma energy & core electron temperature, reduced plasma-wall interaction, and an up to one order of magnitude reduction in plasma turbulence across the whole plasma radius in the frequency range 5 to 500 kHz. In addition, and contrary to expectations for high-density plasmas in stellarators, it is seen, when injecting TESPELs to deposit tracers in the core of this high-performance phase, that impurity confinement is significantly reduced for plasmas with Li powder when compared to confinement in discharges without Li-powder. These new results demonstrate the potential of continuous dropping of Li-powder into stellarator plasmas for simultaneously accessing enhanced confinement regimes while avoiding impurity accumulation.

== Dissemination of project results (peer-reviewed publications and conference presentations) ==

PEER-REVIEWED ARTICLES ASSOCIATED TO THIS PROJECT (SINCE 2021)

[1] Enhanced confinement induced by pellet injection in the stellarator TJ-II, I. García-Cortes, K. J. McCarthy, T. Estrada, V. Tribaldos, B. van Milligen, E. Ascasíbar, R. Carrasco, A. A. Chmyga, R. García, J. Hernández-Sánchez, C. Hidalgo, S. Kozachek, F. Medina, D. Medina-Roque, M. A. Ochando, J. L. de Pablos, N. Panadero, I. Pastor and TJ-II Team, Phys. Plasmas 30 (2023) 072506. https://doi.org/10.1063/5.0151395

[2] Multi-pellet injection into the NBI-heated phase of TJ-II plasmas, K. J. McCarthy, I. García-Cortés, A. Alonso, A. Arias-Camisón, E. Ascasíbar, A. Baciero, A. Cappa, R. Carrasco, O. O. Chmyga, T. Estrada, R. García, J. Hernández-Sánchez, F. J. Herranz, O. S. Kozachok, B. López Miranda, F. Medina, D. Medina-Roque, B. van Milligen, M. Navarro, M. A. Ochando, J. L. de Pablos, N. Panadero, I. Pastor, J. de la Riva, M. C. Rodríguez, D. Tafalla, V. Tribaldos and TJ-II Team, Nucl. Fusion 64 (2024) 066019, https://doi.org/10.1088/1741-4326/ad4047.

[3] Density profiles in stellarators: an overview of particle transport, fueling and profile shaping studies at TJ-II, J. A. Alonso, …, I. García-Cortés, ..., J. Hernández-Sánchez, ..., B. López-Miranda, ..., K. J. McCarthy, ..., D. Medina-Roque, ..., P. Méndez, ..., N. Panadero, ..., N. Tamura, ..., et al., Nucl. Fusion 64 (2024) 112018. https://doi.org/10.1088/1741-4326/ad67ef

[4] Controlling performance bifurcations in stellarators - an inter-machine study of cryogenic-pellet fueling in helical devices, A. Dinklage, ..., I. García-Cortés, ..., K. McCarthy, D. Medina-Roque, ..., N. Tamura, ..., The Heliotron-J Team, The TJ-II Team, The LHD Experiment Team and the W7-X Team, sent to Nucl. Fusion, NF-107510.

[5] The effect of pellet injection on turbulent transport in TJ-II, L. García, I. García-Cortés, B. A. Carreras, K. J. McCarthy, B. van Milligen and TJ-II team, Phys. Plasmas 30 (2023) 092303. https://doi.org/10.1063/5.0163832

[6] The rotational transform and enhanced confinement in the TJ-II stellarator, B. Ph. van Milligen, I. García-Cortés, K. J. McCarthy, B. A. Carreras, L. García, A. Cappa, P. Pons-Villalonga, T. Estrada, D. Medina-Roque, J. Hernández-Sánchez, R. garcía, O. S. Kozachok, O. O. Chmyga, J. L. de Pablos, J. M. Barcala, A. Molinero, I. Pastor, D. Tafalla, A. de la Peña, F. Lapayese and the TJ-II Team, J. Plasma Physics 91 (2025) E98. https://doi.org/10.1017/S0022377825100433.

[7] Overview of the TJ-II stellarator research programme towards model validation in fusion plasmas, C. Hidalgo, ..., I. García-Cortés, ..., J. Hernández-Sánchez, ..., B. López-Miranda, ..., K. J. McCarthy, ..., P. Méndez, ..., N. Panadero, ..., N. Tamura, ..., et al., Nucl. Fusion 62 (2022) 042025, https://doi.org/10.1088/1741-4326/ac2ca1

[8] Using rational surfaces to improve pellet fuelling efficiency in stellarators, N. Panadero, K. J. McCarthy, B. Pégourié, R. Carrasco, I. García-Cortés, R. García, J. Hernández-Sánchez, F. Köchl, J. Mártinez-Fernández, and R. Sakamoto, J. Plasma Phys. 89 (2023) 955890601. https://doi:10.1017/S0022377823001010.

[9] A comparison of the influence of plasmoid-drift mechanisms on plasma fuelling by cryogenic pellets in ITER and Wendelstein 7-X, N. Panadero, F. Koechl, A. R. Polevoi, J. Baldzuhn, C. D. Beidler, P. Lang, A. Loarte, A. Matsuyama, K. J. McCarthy, B. Pégourié, and Y. Turkin, Nucl. Fusion 63, 046022 (2023). https://doi.org/10.1088/1741-4326/acbc34

[10] Commissioning of the Tracer-Encapsulated Solid Pellet (TESPEL) Injection system for Wendelstein 7-X and first results, R. Bussiahn, N. Tamura, K. J. McCarthy, B. Buttenschön, C. Brandt, A. Dinklage, A. Langenberg and the W7-X team, Plasma Phys. Control. Fusion, 66 (2024) 115020. https://doi.org/10.1088/1741-4326/ac2cf5.

[11] Additional ECRH mitigates thermal quenches induced by tungsten TESPEL injection in LHD, H. Bouvain, A. Dinklage, N. Tamura, H. Igami, H. Kasahara, K. J. McCarthy, D. Medina Roque, I. García-Cortés and the LHD Experiment Group, sent to Nuclear Fusion for publication, NF-106861.

[12] Experimental confirmation of efficient island divertor operation and successful neoclassical transport optimization in Wendelstein 7-X, T. S. Pedersen, ..., I. García-Cortés, K. J. McCarthy, …, N. Panadero Alvarez, ..., N. Tamura, ..., Nucl Fusion 62, 042022 (2022). https://doi.org/10.1088/1741-4326/ac2cf5

[13] Overview of the first Wendelstein 7-X long pulse campaign with fully water-cooled plasma facing components, O. Grulke, …, R. Bussiahn, ..., I. García-Cortés, ..., K. J. McCarthy, ..., D. Medina Roque, …, N. Panadero Alvarez, ..., N. Tamura, et al., Nucl Fusion 62 (2024) 112002. https://doi.org/10.1088/1741-4326/ad2f4d.

[14] Overview of Large Helical Device experiments of basic plasma physics for solving crucial issues in reaching burning plasma conditions , K. Ida, ..., D. Medina-Roque, ..., I. García-Córtes, ... K. J. McCarthy, …, et al., Nucl. Fusion 64, 112009 (2024). https://doi.org/10.1088/1741-4326/ad3a7a

[15] Reduction of impurity confinement times in lithium-powder induced reduced-turbulence plasmas in the LHD, D. Medina-Roque, F. Nespoli, I. García-Cortés, K. J. McCarthy, N. Tamura, C. Suzuki, M. Goto, T. Kawate, Y. Kawamoto, M. Yoshinuma, K. Ida, K. Tanaka, T. Tokuzawa, H. Funaba, I. Yamada and the LHD team, in preparation for Nucl. Fusion Lett.

POSTERS AND TALKS IN CONFERENCES SINCE 2021

1) TESPEL: a powerful tool for investigating impurity control in the plasma core of magnetic confinement fusion devices, K. J. McCarthy, N. Tamura, R. Bussiahn, N. Takano, F. Reimold, I. García-Cortés, D. Medina-Roque, LHD team, W7-X team, TJ-II team, Invited talk at the 33rd Symposium on Fusion Technology, Dublin, Ireland (2024).

2) Achieving high-performance plasma scenarios in the stellarator TJ-II using cryogenic pellet injection, K. J. McCarthy, I. García-Cortés, J. A. Alonso, A. Baciero, R. Carrasco, O. O. Chmyga, T. Estrada, L. García, R. García, J. Hernández-Sánchez, O. S. Kozachok, B. López Miranda, F. Medina, D. Medina-Roque, B. van Milligen, M. Navarro, J. L. de Pablos, N. Panadero, I. Pastor, J. de la Riva, V. Tribaldos, and TJ-II Team, Invited talk at the 24th International Stellarator Helitotron Workshop, Hiroshima, Japan (2024).

3) Validation of pellet deposition physics by simulation/experiment comparisons on helical devices, N. Panadero, K. J. McCarthy, J. Baldzuhn, G. Motojima, R. Sakamoto, K. Nagasaki, F. Köchl and TJ-II, W7-X, LHD and Heliotron J teams, Invited talk at the 49th EPS Conference on Plasma Physics, Bordeaux, France (2023).

4) Is core fuelling by pellets in helical devices as straightforward as envisaged? An overview of simulation results with the HPI2 code in helical devices, N. Panadero, K. J. McCarthy, J. Baldzuhn, G. Motojima, R. Sakamoto, K. Nagasaki, and F. Köchl, Invited talk at the 23nd International Stellarator-Heliotron Workshop, Warsaw, Poland (2022).

5) Enhanced confinement after multi-pellet injection into neutral beam injection heated plasmas in the stellarator TJ-II, K. J. McCarthy, I. García-Cortés, A. V. Melnikov, N. Panadero, E. Ascasíbar, M. Drabinskiy, L. G. Eliseev, T. Estrada, J. Hernández-Sánchez, P. Khabanov, A. S. Kozachek, M. Liniers, S. E. Lysenko, D. Medina-Roque, P. Medina, M. A. Ochando, J. L. de Pablos, I. Pastor, C. Toledo, B. van Milligen, & TJ-II team, Oral talk at the 48th EPS Conf. Plasma Phys., Maastricht, The Netherlands (2022).

6) Pellet injection in the stellarator TJ-II for fuelling and impurity control studies, I. García-Cortés, K. J. McCarthy, D. Medina-Roque, N. Tamura, A. Baciero, R. Carrasco, O. O. Chmyga, T. Estrada, R. García, J. Hernández-Sánchez, O. S. Kozachok, B. López Miranda, F. Medina, B. van Milligen, M. Navarro, J. L. de Pablos, N. Panadero, I. Pastor, J. de la Riva, V. Tribaldos and TJ-II Team, Oral talk at the XXXIX Reunión Bienal de la Real Sociedad Español de Física, Donostia/San Sebastián, Spain (2024).

7) Enhanced-performance scenarios in the stellarator TJ-II using pellet injection, I. García-Cortés, K. J. McCarthy, D. Medina-Roque, A. Baciero, R. Carrasco, O. Chmyga, T. Estrada, L. García, J. Hernández-Sánchez, O. S. Kozachok, B. López Miranda, F. Medina, B. van Milligen, N. Panadero, I. Pastor, J. de la Riva, D. Tafalla, V. Tribaldos, and the TJ-II Team, Oral talk at the 50th EPS Conference on Plasma Physics, Salamanca, Spain (2024).

8) Controlling performance bifurcations in large stellarators, an intermachine study of cryogenic fueling in helical devices, A. Dinklage, …, A. Alonso, … I. García-Cortés, …, K. McCarthy, … N. Panadero, et al., the TJ-II team, Oral talk at the 29th Fusion Energy Conference, London, England (2023).

9) Enhanced plasma performance after pellet injections in the stellarator TJ-II, K. J. McCarthy, I. García-Cortés, V. Tribaldos, T. Estrada, D. Medina Roque, B. van Milligen, N. Panadero, E. Ascasíbar, R. Carrasco, R. García, J. Hernández Sánchez, B. López Miranda, A. S. Kozachek, I. Pastor, A. A. Chmyga, and TJ-II team, 29th IAEA-Fusion Energy Conference, Poster presentation at the 29th Fusion Energy Conference, London, England (2023).

10) Physics Studies of Cryogenic Pellet and Tracer-loaded Pellet (TESPEL) injections in the Stellarator TJ-II, K. J. McCarthy, N. Panadero, I. García Cortes, E. Ascasíbar, A. Cappa, J. M. Fontdecaba, J. Hernández Sánchez, M. Liners, I. Pastor, TJ-II Team, N. Tamura, and G. Motojima, Poster presentation at the 28th IAEA-FEC Conference, Nice, France (2021).

12) Influence of the magnetic well on pellet fuelling in the TJ-II stellarator, N. Panadero, K. J. McCarthy, I. García Cortés, B. López Miranda, et al., and TJ-II Team, Poster presentation at the 24th International Stellarator Helitotron Workshop, Hiroshima, Japan (2024).

13) A study on Z-dependence of impurity confinement and transport in turbulence reduced plasmas via lithium powder injection in LHD, D. Medina-Roque, I. García-Cortés, K. J. McCarthy, N. Tamura, F. Nespoli, C. Suzuki, M. Goto, T. Kawate, Y. Kawamoto, M. Yoshinuma, K. Ida, K. Tanaka, T. Tokuzawa, H. Funaba, I. Yamada and the LHD team, Poster presentation at the 50th EPS Conference on Plasma Physics, Salamanca, Spain (2024).

14) Neoclassical analysis of the enhanced-performance scenarios in the stellarator TJ-II after pellet injection, V. Tribaldos, I. García-Cortés, B. Ph. van Milligen, K. J. McCarthy and TJ-II team, Poster presentation at the 50th EPS Conference on Plasma Physics, Salamanca, Spain (2024).

15) Impact of low order rationals in the enhanced confinement by pellet injection in TJ-II, L. García, B. A. Carreras, I. García-Cortés, B. Ph. van Milligen, K. J. McCarthy and TJ-II team, Poster presentation at the 50th EPS Conference on Plasma Physics, Salamanca, Spain (2024).

16) Characterization of the impact of pellet injections on fast-ion losses in NBI plasmas in the TJ-II stellarator, B. López-Miranda, N. Panadero, C. Salcuni, Á. Cappa, A. Baciero, R. García, I. García-Cortés, J. Hernández-Sánchez, D. Jiménez-Rey, D. López-Bruna, D. Medina, F. Medina, K. J. McCarthy, I. Pastor, J. de la Riva, Poster presentation at the 50th EPS Conference on Plasma Physics, Salamanca, Spain (2024).

17) Additional ECRH mitigates thermal quenches induced by tungsten TESPEL injection in LHD, H. Bouvain, A. Dinklage, N. Tamura, H. Kasahara, R. Bussiahn, K. McCarthy, D. Medinaand the LHD Team, Poster presentation at the 29th IAEA Fusion Energy Conference, London, England (2023).

18) TESPEL studies on the Z-dependence of impurity transport in different plasma scenarios in LHD, D. Medina, N. Tamura, I. García-Cortés, K. J. McCarthy & LHD team, 49th EPS Conf. Plasma Phys., Bordeaux, France (2023).

19) Studying fast-ion losses induced by Alfvén Eigenmodes and by pellet injection in NBI heated plasmas of the stellarator TJ-II, B. López-Miranda, A. Baciero, D. Jiménez-Rey, K. J. McCarthy, I. García-Cortés, N. Panadero, D. Medina-Roque, J. Hernández Sánchez, A. Cappa, P. Pons, F. Medina, and I. Pastor, 49th EPS Conf. Plasma Phys., Bordeaux, France (2023).

20) Enhanced confinement induced by multi-pellet injection into neutral beam injection heated plasmas in the stellarator TJ-II, I. García-Cortés, K. J. McCarthy, V. Tribaldos, D. Medina-Roque, N. Panadero, E. Ascasíbar, T. Estrada, J. Hernández-Sánchez, A. S. Kozachek, M. Liniers, S. E. Lysenko, D. Medina-Roque, P. Medina, M. A. Ochando, J. L. de Pablos, I. Pastor, B. van Milligen & TJ-II team, Poster presentation at the 49th EPS Conf. Plasma Phys., Bordeaux, France (2023).

21) On the radial pellet cloud drift in stellarator plasmas, G. Kocsis, J. Baldzuhn, C. Biedermann, R. Bussiahn, A. Buzás, G. Cseh, I. García-Cortés, M. Krause, K. J. McCarthy, D. Medina-Roque, N. Panadero, T. Szepesi, N. Tamura, Th. Wegner, TJ-II team and W7-X team, Poster presentation at the 49th EPS Conf. Plasma Phys., Bordeaux, France (2023).

22) New Insights into cryogenic and TESPEL pellet physics in TJ-II, D. Medina-Roque, I. García-Cortés, K. J. McCarthy, N. Tamura, N. Panadero, E. Ascasíbar, T. Estrada, J. Hernández-Sánchez, A. S. Kosachek, M. Liniers, P. Medina, M. A. Ochando, J. L. de Pablos, I. Pastor, C. Toledo, B. van Milligen & TJ-II team, Poster presentation at the 48th EPS Conf. Plasma Phys., Maastricht, The Netherlands (2022).

23) Pellet studies with an upgraded fast-camera system in the stellarator TJ-II, N. Panadero, G. Kocsis, T. Szepesi, K. J. McCarthy, G. Motojima, E. de la Cal, J. Hernández Sánchez, A. Ros, and TJ-II Team, Poster presentation at the 47th EPS Conference on Plasma Physics, On-line Event (2020/21).

24) Impurity transport studies on Wendelstein 7-X by Tracer-Encapsulated Solid Pellets, R. Bussiahn, N. Tamura, K.J. McCarthy and the W7-X team, Poster presentation at the 47th EPS Conference on Plasma Physics, On-line Event (2020/21).

(25) Spatio-temporal structure of pellet-plasmoid in high-temperature plasmas, G. Motojima, S. Kado, S. Ohshima, A. Mori, T. Suzuki, N. Panadero, K. J. McCarthy, M. Goto, R. Sakamoto, and K. Nagasaki, Plenary talk at 6th Asia Pacific Conference on Plasma Physics, Division of Plasma Physics, Association of Asia-Pacific Physical Societies, Division of Plasma Physics, e-conference (2022).

(26) Magnetic configuration effects on pellet fuelling in stellarators, N. Panadero, K.J. McCarthy, J. Baldzuhn, J. Hernández-Fernández, F. Köchl, G. Kocsis, A. I. Mohammed, N. Tamura, M.B. Vavrik, E. Villalobos Granados, T. Szepesi, and TJ-II and W7-X teams, Oral presentation at 51st EPS Conference on Plasma Physics, Vilnius, Lithuania (2025).

(27) Study of the density limit physics for stellarator devices by means of an energy balance model, J. Gallego, A. Alonso, A. Bustos, T. Estrada, B. López-Miranda, A. Baciero, A. Cappa, K. J. McCarthy, I. García-Cortés, J. de la Riva Villén, F. Medina, N. Panadero and the TJ-II Team, poster presentation at 51st EPS Conference on Plasma Physics, Vilnius, Lithuania (2025).


<hr>
[[LNF:Nationally Funded Projects|Back to list of nationally funded projects]]

[[Category:LNF Nationally Funded Projects - finished]]

LNF: (2022-2024) Estudio experimental de flujos, turbulencia y modos MHD, y su impacto en confinamiento en los stellarators TJ-II y W7-X

2025-12-10T10:20:43Z

Elena.delaluna: /* Description of the project */

== LNF - Nationally funded project ==

'''Title''': '''Estudio experimental de flujos, turbulencia y modos MHD, y su impacto en confinamiento en los stellarators TJ-II y W7-X'''

'''Reference''': PID2021-125607NB-I00

'''Programme and date''': Proyectos de Generación de Conocimiento Año 2021

'''Programme type (Modalidad de proyecto)''': Proyectos de investigación no orientada

'''Area/subarea (Área temática / subárea)''': Ciencias Físicas / Física y sus aplicaciones

'''Principal Investigators''': [https://orcid.org/0000-0001-6205-2656 Teresa Estrada] and [https://orcid.org/0000-0002-7824-3307 Daniel Carralero]

'''Project type''': Proyecto individual

'''Start-end dates''': 01/01/2022 - 31/12/2024

'''Financing granted (direct costs)''': 160.000,00 €

== Description of the project ==

The main objective of the present proposal is to study a family of instabilities present in the strongly magnetized plasmas required for the development of a practical nuclear fusion reactor, which range from the electrostatic drift turbulence typically dominating transport among thermal populations of confined species, to magneto-hydrodynamic modes destabilized by fast ion populations, such as the Alfvèn Eigenmodes, as well as the potential interactions between them. Finding mechanisms by which these instabilities can be suppressed or controlled in reactor-relevant conditions is critical for the achievement of the high plasma confinement required for an economical exploitation of nuclear fusion. With this aim, we propose the experimental characterization of these instabilities and the plasma conditions driving them, followed by its interpretation under the best available theoretical frameworks. This project can be seen as a continuation and expansion of the previous FIS2017-88892-P grant, in which related research was carried out in the TJ-II and Wendelstein 7-X (W7-X) stellarators, including the commissioning and operation of several relevant diagnostics. From there, our work plan assesses the current state of the research and defines several lines of work such as turbulence stabilization during post-pellet phases, fluctuation and potential asymmetries, flow departure from neoclassical theory, NBI destabilization of AE modes, detection and characterization of zonal flows, etc.

TJ-II is the flagship of the National Laboratory for Fusion (LNF) and part of the Spanish ICTS catalogue. As members of the LNF, the proponents have full access to TJ-II, where the several diagnostics relevant for the study are available. In particular, a steerable Doppler reflectometry (DR) system provides the simultaneous measurement of fluctuations and flows, allowing for very detailed studies of turbulence, critical for the characterization of drift modes. As well, a helical array of Mirnov coils has been recently added to TJ-II, allowing for a detailed study of AEs, including their complex 3D structure in non-axisymmetric devices. W7-X is sited in the Max-Planck-Institut für Plasmaphysik (IPP) in Greifswald. W7X is the largest stellarator in the world and was built to reproduce a number of reactor-relevant features such as optimized magnetic field, high beta operation or actively cooled island divertor. Since 2015, the LNF has collaborated with IPP in the development of a DR system, which has already been successfully operated in previous experimental campaigns. Presently, this system is being refurbished including a number of improvements which will greatly expand the scope of the experimental measurements which can be carried out. As well, a new diagnostic has been included in the proposal: A Charge eXchange Recombination Spectroscopy (CXRS) system, which will complement the investigation of plasma flows carried out by the DR. These diagnostics will ensure access to experimental data in reactor-relevant conditions during the forthcoming OP2.1-OP2.3 campaigns, scheduled for the 2022-2024 period. On top of these purely experimental activities, we outline the data analysis and comparison of physical results to numerical simulations of turbulence (gyrokinetic codes), AE stability (gyrofluid codes), plasma profiles (neoclassical codes) or synthetic DR response to plasma conditions (2D full wave code).

== Main results ==

Enter text here (summary of main project results from the final report)

== Dissemination of project results (peer-reviewed publications and conference presentations) ==

== References ==
<references />


<hr>
[[LNF:Nationally Funded Projects|Back to list of nationally funded projects]]

[[Category:LNF Nationally Funded Projects - finished]]

LNF:Project template

2025-12-10T10:19:13Z

Elena.delaluna: /* Project documentation */

LNF:L2HPED Estudio de Transiciones L-H y Pedestal en Modo H en Tokamaks (2022-2026)

2025-12-10T10:03:37Z

Elena.delaluna: /* Project Documentation */

== LNF - Nationally funded project ==

'''Title''': '''Estudio de Transiciones L-H y Pedestal en Modo H en Tokamaks / Study of L-H transitions and H-mode pedestal in tokamaks (L2HPED) '''

'''Reference''': PID2021-127727OB-I00

'''Funding Umbrella''': Plan Estatal de Investigación Científica y Técnica y de Innovación 2021-2023

'''Funding Programme''': Programa Estatal para Impulsar la Investigación Científico-Técnica y su Transferencia

'''Subprogramme''': Subprograma Estatal de Generación de Conocimiento

'''Programme and date''': Proyectos de Generación de Conocimiento 2021

'''Programme type/ Modalidad''': Investigación Orientada Tipo B

'''Area/subarea''': Ciencias Físicas/Física y sus aplicaciones

'''Principal Investigator(s)''': [http://orcid.org/0000-0002-4815-3407 Emilia R. Solano] and [https://orcid.org/0000-0002-5420-0126 Elena de la Luna]

'''Project type''': Individual

'''Start-end dates''': 01/09/2022 - 31/08/2026

'''Financing granted (direct costs/indirect costs)''': €90,000 / €18,900

'''Acknowledgement''': Grant PID2021-127727OB-I00 funded by MCIN/AEI/10.13039/501100011033 and by ERDF A way of making Europe

== Description of the project ==

Con este proyecto queremos mejorar la calidad de las predicciones sobre los plasmas de ITER y DEMO, que son los próximos equipos de
fusión y el foco del programa de confinamiento magnetico europeo.

La propuesta aborda 3 aspectos fundamentales de la operación de ITER asociados a la física del pedestal: la transición L-H, regímenes
de ELMs pequeños, y el "Quiescent H-mode", también llamado mode QH, sin ELMs.

En cuanto a la transición L-H, proponemos continuar el trabajo experimental en el JET, especialmente ahora que hemos empezado a
obtener datos de la transición L-H en mezclas de tritio y deuterio-tritio (las más relevantes para la fusión), en el JET-ILW, con pared de Be y divertor de Wolframio. El trabajo experimental de la transición L-H implica la coordinación del equipo, el diseño del experimento, la preparación, la ejecución, el análisis de los datos y su interpretación.

En términos de la teoría L-H, estamos investigando la naturaleza del modo M, una oscilación magnética n=0, m=1 observada en el inicio
del modo H. En los datos disponibles de los estudios de transición LH en plasmas calentados por radio-frecuencia en JET, la frecuencia del modo M parece escalar con la corriente de plasma dividida por la raíz cuadrada de la densidad de masa de los iones, lo que indica que posiblemente sea una onda poloidal de Alfvén. Nuestro objetivo es desarrollar modelos analíticos y numéricos de ondas Alfvén poloidales superficiales, para explicar las frecuencias observadas empíricamente.

Experimentos recientes en JET-ILW han demonstrado que es posible obtener simultáneamente buen confinamiento en modo H, en
condiciones estacionarias para la densidad y la temperature y con ELMs pequeños. Estos resultados se han obtenido con baja
collisionalidad en el pedestal y utilizando el escenario básico (Baseline) de ITER (con <math>q_{95}=3</math>, <math>H_{98}=1</math> y <math>\beta_N=2</math>). Esto hace de este nuevo regimen de operacion muy diferente de lo que se ha observado previamente en otros dispositivos de fusion (AUG, DIII-D y JT-60U. En este proyecto nos proponemos investigar la física responsable de la aparición de ELMs pequeños, el buen confinamiento y la ausencia de acumulación de impurezas en estas condiciones. Pretendemos contribuir a una mejor comprensión de los mecanismos físicos que afectan a la estabilidad del pedestal, a la turbulencia y al transporte de impurezas en la región del pedestal y del núcleo y, como resultado, contribuir a aumentar la precisión de las extrapolaciones para el ITER y otros dispositivos futuros.

En cuanto a los regímenes sin ELMs, proponemos investigar el modo QH. El modo QH es un estado estacionario del plasma, de interés
potencial para ITER y DEMO. Ha sido una prioridad del programa DIII-D porque permite el acceso a pedestales calientes con alto
confinamiento del núcleo y sin ELMs. No se sabe si puede desarrollarse y mantenerse con un diveror de Wolframio y una pared de Berilio.

Actualmente, Eurofusion está considerando la posibilidad de realizar futuros experimentos en modo QH en las campañas experimentales
del JET 2022-2023. Si se aprueba, este proyecto contribuiría a ellos. En cualquier caso, nos uniríamos a la colaboración entre AUG y DIIID para ejecutar y analizar experimentos de similitud.

== Project Documentation ==
* [https://wiki.fusion.ciemat.es/fusionwiki/images/9/9c/Memoria-cientifico-tecnica-individual-2021_final.pdf Memoria Cientifico Tecnica - Convocatoria 2021 "Proyectos de Generación de Conocimientos"]
* [https://wiki.fusion.ciemat.es/fusionwiki/images/6/6c/Informe_Intermedio_PID2021_127727OB-I00.pdf Informe Intermedio (Nov/2024)]

'''Follow-up/Seguimiento'''
* Approval/Autorización 13/05/2024, Start Contract: 30/05/2024
* Change request/Solicitud de modificación 16/04/2024, subcontract tomography analysis

== Main results ==
To be completed after submission of final report

== Dissemination of project results (peer-reviewed publications and conference presentations) ==
<references />
'''Peer-reviewed articles directly related to the L2HPED Project (since Sept/2022)'''

# [https://iopscience.iop.org/article/10.1088/1361-6587/ac97c0 Power balance analysis at the L-H transition in JET-ILW NBI-heated deuterium plasmas] P Vincenzi, E.R. Solano et al. Plasma Phys. Control. Fusion 64, 124004 (2022)
# [https://iopscience.iop.org/article/10.1088/1741-4326/ac97f4/meta Effect of the divertor configuration on the JET edge radial electric field] C Silva, ER Solano, et al, Nuclear Fusion 62 (12), 126057 (2022)
# [https://iopscience.iop.org/article/10.1088/1361-6587/acc423/meta The role of isotope mass and transport for H-mode access in tritium containing plasmas at JET with ITER-like wall], G Birkenmeier, ER Solano, ... E de la Luna et al, Plasma Physics and Controlled Fusion 65 (5), 054001 (2023)
# [https://iopscience.iop.org/article/10.1088/1741-4326/acee12 LH transition studies in tritium and deuterium–tritium campaigns at JET with Be wall and W divertor], E.R. Solano, G. Birkenmeier, C. Silva, E. Delabie, J.C. Hillesheim, (…), E. de la Luna, et al., Nuclear Fusion 63, 112011 (2023) (Special Issue of Papers Presenting Results from the JET Tritium and Deuterium/Tritium Campaign)
# [https://iopscience.iop.org/article/10.1088/1741-4326/ad0eae Experimentally corroborated model of pressure relaxation limit cycle oscillations in the vicinity of the transition to high confinement in tokamaks] O. Grover, P. Manz, A.Y. Yashin, D.I. Réfy, J. Seidl, N. Vianello, G. Birkenmeier, E.R. Solano et al, Nucl. Fusion 64, 026001 (2024)
# [https://iopscience.iop.org/article/10.1088/1741-4326/ac97f4/meta Exploring the physics of a high-performance H-mode scenario with small ELMs at low collisionality in JET with Be/W wall] E. de la Luna, J. Garcia, M. Sertoli, ... E.R. Solano et al., Nuclear Fusion 64, 096014 (2024)
# [https://iopscience.iop.org/article/10.1088/1741-4326/ad6335/pdf Helium plasma operations on ASDEX Upgrade and JET in support of the non-nuclear phases of ITER] A. Hakola et al., Nucl. Fusion 64, 096022 (2024)
# [https://www.nature.com/articles/s41467-024-52182-z Stable Deuterium-Tritium plasmas with improved confinement in the presence of energetic-ion instabilities] J. Garcia, Y. Kazakov, R. Coelho, M. Dreval, E. de la Luna, E.R. Solano et al. Nature Communications 15, 7846 (2024)
# [https://iopscience.iop.org/article/10.1088/1361-6587/ad867b Turbulent transport mechanisms and their impact on the pedestal top of JET plasmas with small-ELMs] M. Dicorato, M. Muraglia, Y. Camenen, J. García... E. de la Luna, et al., Plasma Phys. Control. Fusion 66, 125002 (2024)
# [https://iopscience.iop.org/article/10.1088/1741-4326/ad96cd/meta Non-linear dependence of ion heat flux on plasma density at the L-H transition of JET NBI-heated Deuterium-Tritium plasmas.] P. Vincenzi, E.R. Solano et al, Nucl. Fusion 65 016038 (2025)
# [https://doi.org/10.1088/1741-4326/ad8ced Transport and confinement physics: Chapter 2 of the special issue: on the path to tokamak burning plasma operation] M. Yoshida (Chair Transport and Confinement) et al Nucl. Fusion 65 033001 (2025)
# [https://iopscience.iop.org/article/10.1088/1741-4326/adb762/meta Er measurements in JET L-mode plasmas for a wide range of densities—from the low-recycling regime up to the density limit] C Silva et al, Nuclear Fusion 65 (3), 036042 (2025)
# [https://iopscience.iop.org/article/10.1088/1741-4326/adb1f3 Progress in pedestal and edge physics: Chapter 3 of the special issue: on the path to tokamak burning plasma operation] M.E. Fenstermacher (Chair, Pedestal and Edge Physics), L.R. Baylor, E. de la Luna, M.G. Dunne, G.T.A. Huijsmans, et al. Nucl. Fusion 65 053001 (2025) (ITPA results Special Issue)
# [https://doi.org/10.1016/j.nme.2025.101904 The quasi-continuous exhaust regime in ASDEX Upgrade and JET] M. Faitsch et al, Nuclear Materials and Energy 42 101904 (2025)
# [https://doi.org/10.1088/1741-4326/adaf41 ITER NBI operational window and power availability constraints due to shine-through losses] P. Vincenzi et al Nucl. Fusion 65 036009 (2025)
# [https://doi.org/10.1088/1361-6587/adbb1a Connecting recent JET isotope L-H transition studies to H-mode access in new ITER scenarios] Pietro Vincenzi et al Plasma Physics and Controlled Fusion 67 (4), 045013 (2025)
# [https://iopscience.iop.org/article/10.1088/1741-4326/adb762/meta Er measurements in JET L-mode plasmas for a wide range of densities—from the low-recycling regime up to the density limit] C. Silva et al Nucl. Fusion 65 036042 (2025)
# [https://doi.org/10.1016/j.fpp.2025.100096 Fusion research in a Deuterium-Tritium tokamak] Emilia R. Solano Fundamental Plasma Physics 15, 100096 (2025)
# [https://iopscience.iop.org/article/10.1088/1741-4326/ae03d6 Isotope mix effect on edge turbulent transport in pre-L–H transition conditions in JET-ILW], G Lo-Cascio, N Bonanomi, C Angioni, G Birkenmeier, ER Solano, et al Nuclear Fusion 65 (10), 106034 (2025)
# [https://iopscience.iop.org/article/10.1088/1741-4326/ad8ced/meta Chapter 2 of the special issue: on the path to tokamak burning plasma operation], M. Yoshida et al (..., ER Solano,...) 2025 Nucl. Fusion 65 033001
# [https://iopscience.iop.org/article/10.1088/1361-6587 Overview of the third JET deuterium-tritium campaign], A Kappatou et al (E.R. Solano), Plasma Phys. Control. Fusion 67, 045039 (2025)
# [https://doi.org/10.1088/1361-6587/adc8d0 Psep/PLH control in deuterium and deuterium–tritium JET plasmas], L. Piron et al (E.R. Solano), Plasma Phys. Control. Fusion 67, 055006 (2025)
# E Delabie et al (E.R. Solano), Empirical scaling of the L-H threshold power for metal wall tokamaks using a multi-device database submitted Nuclear Fusion (Aug 2025)

'''Conferences related to the L2HPED Project (since Sept/2022)'''

# Observation of Edge Harmonic Oscillations in JET-ILW Deuterium (poster) E.R. Solano, P. Buratti, J.M. Fontdecaba, D. Brunnetti, E. Viezzer et al. 64th Annual Meeting of the APS Division of Plasma Physics, Spokane, Washington, USA (October 17-21, 2022)
# ELMy H-mode Helium plasma at JET-ILW (oral) M. Maslov, M. Dunne, L. Garzotti, R. Henriques, A. Loarte, C. Lowry, E.R. Solano, O. Sauter, P. Bohm, P Bilkova and JET Contributors 49th EPS Conference on Plasma Physics, Bordeaux, France (July 3-7, 2023)
# Influence of impurity radiation loss on the LH transition power threshold (poster) E. Pawelec, W. Gromelski, A. Chomiczewska, E.R. Solano, …, J.C. Hillesheim, et al. 49th EPS Conference on Plasma Physics, Bordeaux, France (July 3-7, 2023)
# The L-H transition: new results from the JET Tritium and Deuterium-Tritium campaigns (plenary) E.R. Solano et al. Plasma 2023 – International Conference on Research and Applications of Plasmas, Warsaw, Poland (18 September 2023)
# Characterization of L-H transition density branches in JET D-T plasmas through a power balance analysis (poster) P. Vincenzi, E.R. Solano, P. Carvalho, E. Delabie et al. 20th European Fusion Theory Conference, Padova, Italy (October 2-5, 2023)
# Gyrokinetic Simulations of JET pedestal top plasmas in different regimes (poster). M. Dicorato, M. Muraglia, Y. Camenen, J. García, X. Garbet, et al. 20th European Fusion Theory Conference, Padova, Italy (October 2-5, 2023)
#[https://wiki.fusion.ciemat.es/fusionwiki/images/e/e2/109479_ersolano_jet_l2h_pinboard_1_20.pdf L-H transition physics results from recent tritium and deuterium-tritium campaigns at JET (oral)]. E. R. Solano et al. 29th IAEA Fusion Energy Conference, London, UK (16-21 Octubre, 2023) IAEA-CN-316 (EX/2-1)
# [https://wiki.fusion.ciemat.es/fusionwiki/images/d/db/DelaLuna_8pages_FEC2023.pdf Experimental conditions to access high-performance H-mode plasmas with small ELMs at low collisionality in JET-ILW (poster)] E. de la Luna, M. Dunne, P. Lomas, C. Reux, E. R. Solano, J. García, M. Faitsch, M. Poradzinski, G. Pucella, S. Mennuir, R. Coelho, B. Labit, O. Sauter, E. Viezzer, M. Wischmaier, JET contributors and the EUROfusion Tokamak Exploitation team. . 29th IAEA Fusion Energy Conference, London, UK (16-21 Octubre, 2023) IAEA-CN-316 (EX/P-2603)
# [https://wiki.fusion.ciemat.es/fusionwiki/images/2/2a/109816_ersolano_jet_l2h_itpa_oct2023.pdf L-H TRANSITION RESULTS FROM RECENT TRITIUM AND DEUTERIUM-TRITIUM CAMPAIGNS AT JET (oral)]. E. R. Solano and the JET L-H transition team. 42nd ITPA PEP Meeting, Culham, UK, 23rd October 2023.
# [https://wiki.fusion.ciemat.es/fusionwiki/images/f/f1/EdelaLuna_SmallELMs_ITPA_23Oct2023.pdf HIGH-PERFORMANCE PLASMAS WITH SMALL ELMS AT LOW COLLISIONALITY IN JET-ILW (oral)]. E. de la Luna, M. Dunne, P. Lomas, C. Reux, E.R. Solano, J. García, M. Faitsch, M. Poradzinski, G. Pucella and JET contributors. 42nd ITPA PEP Meeting, Culham, UK, 23rd October 2023.
# [https://wiki.fusion.ciemat.es/fusionwiki/images/1/1d/Dicorato_EPS2024_presentation_v8.pdf Turbulent transport at the pedestal top of small-ELM plasmas at JET: key mechanisms and their impact (oral)] M. Dicorato, M. Muraglia, Y. Camenen, J. García, X. Garbet, D.R. Hatch, G. Merlo, E. de la Luna and JET Contributors. 50th EPS Conference on Plasma Physics Salamanca, (8-12 July, 2024)
# [http://documenta.ciemat.es/bitstream/123456789/3160/1/Solano_EPS_JET_poster_020724.pdf Potential research programme for JET with W wall and ECRH (poster)]and [http://documenta.ciemat.es/bitstream/123456789/3180/1/Solano_P1.048.pdf paper] by E. R. Solano, J. Ongena and JET petition contributors. 50th EPS Conference on Plasma Physics Salamanca, (8-12 July, 2024). Winner of the People's choice award for the best poster of the conference.
# [https://wiki.fusion.ciemat.es/fusionwiki/images/c/c0/EdelaLuna_H-mode_Workshop_2024_oral_v2.pdf Pedestal structure and stability of high-performance scenarios with I-mode-like pedestals in JET with the Be/W wall (oral)] and [https://wiki.fusion.ciemat.es/fusionwiki/images/5/5e/DelaLuna_poster_HMW2024_v2.pdf (poster)] E. de la Luna, J. García, M. Dunne, Y. Kazakov, E. R. Solano, E. Delabie, M. Faitsch, L. Frassinetti, JET contributors and the EUROfusion TE team. 19th International Workshop on H-mode Physics and Transport Barriers, Mito (Japan), 21-24 September 2024.
# [https://wiki.fusion.ciemat.es/fusionwiki/images/d/d2/ERSolano_ICPP_2024_final.pdf JET Isotope Studies and the L-H Transition], plenary talk by E. R. Solano, [https://icpp2024.ugent.be/program.html 21st International Congress on Plasma Physics], September 8-13, 2024, Ghent, Belgium.
# [http://users.euro-fusion.org/webapps/pinboard/EFDA-JET/conference/index.html#Document40373 E Delabie] Scaling of the L-H threshold power for metal wall machines: closure of ITPA task TC-26 34th Transport & Confinement ITPA, Cambridge, 28th April 2025
# [http://users.euro-fusion.org/webapps/pinboard/EFDA-JET/conference/index.html#Document40491 PEP-39 Update from JET-ILW: Configuration effects on L-H power threshold and H-mode], E Solano, 45th ITPA meeting of the Pedestal and Edge Physics (PEP) Garching, Germany May 2025
# [http://users.euro-fusion.org/webapps/pinboard/EFDA-JET/conference/index.html#Document40504 A Bayesian approach for the selection of predictor variables in the L-H power threshold scaling in metal-wall machines] P Zhang et al, 6th IAEA TM on Fusion Data Processing, Validation and Analysis, Shanghai, China, 9th September 2025

'''Other publications/conferences derived from collaborations maintained during the execution of the project and that could be relevant to the L2HPED Project (since Sept/2022)'''
# Overview of Deuterium-Tritium results from JET-ILW experiments (invited). E. de la Luna on behalf of JET contributors. 64th Annual Meeting of the APS Division of Plasma Physics, Spokane, Washington, USA (October, 2022, 17-21)
# [https://www.sciencedirect.com/science/article/pii/S2352179122001892 Prospects of core–edge integrated no-ELM and small-ELM scenarios for future fusion devices], E Viezzer,..., E R Solano, Nuclear Materials and Energy 34, 101308 (2023)
# [https://iopscience.iop.org/article/10.1088/1741-4326/acde8d The JET hybrid scenario in Deuterium, Tritium and Deuterium-Tritium] J. Hobirk, CD Challis, A Kappatou, E Lerche, D Keeling, …, J García, …, E de la Luna, …,ER Solano et al. “ Nuclear Fusion 63, 112001 (2023)
# [https://iopscience.iop.org/article/10.1088/1741-4326/ace2d8 JET D-T scenario with optimized non-thermal fusion] M. Maslov, E. Lerche, F. Auriemma, E. Belli, C. Bourdelle, …, J. García, …, E. de la Luna, …,E.R. Solano et al. “ Nuclear Fusion 63, 112002(2023)
# [https://iopscience.iop.org/article/10.1088/1741-4326/acf057 Effect of the isotope mass on pedestal structure, transport and stability in D, D/T and T plasmas at similar βN and gas rate in JET-ILW type I ELMy H-modes] L. Frassinetti, C. Perez von Thun, B. Chapman-Oplopoiou, H. Nystrom, M. Poradzinski, J.C. Hillesheim, …, E.R. Solano et al. Nuclear Fusion 63, 112009 (2023)
# [https://iopscience.iop.org/article/10.1088/1741-4326/acddf8 Divertor power load investigations with deuterium and tritium in type-I ELMy H-mode plasmas in JET with the ITER-like wall] M. Faitsch, I. Balboa, P. Lomas, S.A. Silburn, A. Tookey, D. Kos, A. Huber, E. de la Luna, D. Keeling, A. Kappatou and JET contributors. Nuclear Fusion 63, 112013(2023)
# [https://iopscience.iop.org/article/10.1088/1741-4326/aceb08/meta Experiments in high-performance JET plasmas in preparation of second harmonic ICRF heating of tritium in ITER] M.J. Mantsinen, ..., E. de la Luna,... E.R. Solano et al, Nuclear Fusion 63, 112015 (2023)
# [https://iopscience.iop.org/article/10.1088/1741-4326/ad5c81 Observation of alpha-particles in recent D–T experiments on JET] V.G. Kiptily, …, E. R. Solano,… et al. Nuclear Fusion, 086059 (2024)
# [https://iopscience.iop.org/article/10.1088/1741-4326/ad3e16 Overview of T and D–T results in JET with ITER-like wall] C.F. Maggi et al. Nuclear Fusion 64, 112012 (2024)
# [https://doi.org/10.1007/s41614-025-00182-x Importance of the second D–T campaign at JET for future fusion tokamak devices] J. Garcia et al (E de la Luna, E.R. Solano), Reviews of Modern Plasma Physics Volume 9, article number 10, (2025)
# [https://iopscience.iop.org/article/10.1088/1741-4326/adbe8d/meta Particle fluxes and gross erosion at limiters in JET low-confinement mode plasmas measured with visible cameras] E. de la Cal et al (E.R. Solano), Nucl. Fusion 65 046021 (2025)
# [https://iopscience.iop.org/article/10.1088/1741-4326/addad7 Impact of the plasma boundary on machine operation and the risk mitigation strategy on JET] H.J. Sun et al (E.R. Solano), Nucl. Fusion 65 076012 (2025)

[[File:LogoOficial_PlanNacional_2021.png|500px]]


<hr>
[[LNF:Nationally Funded Projects|Back to list of nationally funded projects]]

[[Category:LNF Nationally Funded Projects]]

LNF:Development of critical diagnostics for the operation of the IFMIF-DONES Lithium target (DONES-LIDIA)

2025-12-10T10:02:22Z

Elena.delaluna: /* Project documentation */

== LNF - Nationally funded project ==

'''Title''': ''' LNF: Development of critical diagnostics for the operation of the IFMIF-DONES Lithium target (DONES-LIDIA, DONES LIthium DIAgnostics)'''

'''Reference''': PID2021-125334OB-I00

'''Programme and date''': Proyectos de Generación de Conocimiento 2021

'''Programme type (Modalidad de proyecto)''': Proyectos investigación orientada

'''Area/subarea (Área temática / subárea)''': Energía y Transporte/Energía

'''Principal Investigator(s)''': David Jiménez-Rey [https://orcid.org/0000-0003-1559-2179]; Cristina de la Morena [https://orcid.org/0000-0001-8470-4571]

'''Project type''': Proyecto individual

'''Start-end dates''': 01/09/2022 - 31/08/2026

'''Financing granted (direct costs)''': 126.000 €

'''Project website''': https://agenda.ciemat.es/e/DONES-LIDIA

== Description of the project ==

The DONES lithium target is one of the most critical parts of the facility, where a high power (5 MW) deuteron beam will impinge on a Li jet flowing at 15 m/s with a temperature of 300 ºC. The interaction between deuteron beam and Li will produce large amount of neutrons (and gamma radiation) with a fusion-like spectrum, which will irradiate the materials under study. The beam power absorption can be performed in a safe way whenever the Li thickness is kept constant during operation in 25 ± 1 mm. This prevents the beam power from impacting in the back plate, which would entail an irreparable damage and the facility shutdown.

The lithium target behavior was studied during the IFMIF-EVEDA phase in 2015 by means of the Li circuit prototype at Orai (Japan). However, the environmental conditions in this experiment were far from DONES ones, as there was no radiation and the diagnostics(based on fast visible camera and laser) were placed in the same position of the beam accelerators in DONES. Therefore, the diagnostics used in this prototype would not be feasible for DONES.
Since 2015 and under Eurofusion WPENS Project, different research institutes have studied how to adapt the diagnostics used in the IFMIF-EVEDA phase to the real operation conditions of DONES: laser diagnostic, contact probes, or visible cameras. Due to the extreme environment conditions in the Li target area, at this moment there is not a planned Li target diagnostic with the robustness and fast response time required for the safe operation of DONES, being a high risk for the facility.

The use of metallic millimeter wave antennas may entail a compact and resistant solution for the harsh environmental conditions. The objective of this project is to define and design a novel and essential diagnostic instrumentation for the DONES Li target based on radiofrequency (RF) with the following functionalities:
(1) Li thickness diagnostic: monitoring of the Li thickness variation in the beam impact area, in communication with the DONES facility, (2) Machine Protection System (MPS) for fast emergency stop, and (3) Surface scanning of the beam impact area for instabilities detection and study of homogeneity and perturbations in the liquid Li flow.

With this purpose, several studies and calculations will be performed to define the compatibility of the equipment under DONES radiation and working conditions: nuclear calculations and radiation-induced accuracy degradation, thermomechanical analysis, and studies of remote handing studies and safety. Finally, a demonstrator will be designed and developed in order to validate the technology and its viability in IFMIF-DONES and extrapolate the results to future fusion reactors.

== Main results ==
To be completed after the submission of the final report



== Dissemination of project results (peer-reviewed publications and conference presentations) ==



== References ==
# A.J. Donné, “Roadmap Towards Fusion Electricity”, Journal of Fusion Energy, 38, 503–505 (2019).
# Ibarra et al., “The IFMIF-DONES project: preliminary engineering design”, Nucl. Fusion, vol. 58 105002, 2018.
# J. Knaster et al., “Overview of the IFMIF/EVEDA project”, Nuclear Fusion, vol. 57, iss. 10, 2017.
# P. Arena, et al., “The design of the DONES lithium target system”, Fusion Engineering and Design, vol. 146, Part A, 2019, pp. 1135-1139, ISSN 0920-3796.
# T. Dézsi, et al., “Overview of the Current Status of IFMIF-DONES Secondary Heat Removal System Design,” Fusion Engineering and Design, vol. 146, Part A, 2019, pp. 430-432, ISSN 0920-3796.
# K. Kondo et al., “Validation of the linear IFMIF prototype accelerator (LIPAc) in Rokkasho,” Fusion Eng. Des. 153, 111503 (2020).
# H. Kondo, et al., “Completion of IFMIF/EVEDA lithium test loop construction”, Fusion Engineering and Design, vol. 87, iss. 5–6, 2012, pp. 418-422.
# A. Aiello, et al., “Lifus (lithium for fusion) 6 loop design and construction”, Fusion Engineering and Design, vol. 88, iss. 6–8, 2013, pp. 769-773.
# E. Wakai, et al., “Engineering validation for lithium target facility of the IFMIF under IFMIF/EVEDA project”, Nuclear Materials and Energy, vol. 9, 2016, pp. 278-285.
# J R Pinzón, et al., “Measurement of the tilt angle of turbulent structures in magnetically confined plasmas using Doppler reflectometry”, Plasma Physics and Controlled Fusion, vol. 61, 10, 2019.
# T. Estrada, et al., “Plasma flow, turbulence and magnetic islands in TJ-II”, Nuclear Fusion, vol. 56, Number 2, 2016.
# M. Fontana, et al., “Real-time applications of Electron Cyclotron Emission interferometry for disruption avoidance during the plasma current ramp-up phase at JET”, Fusion Engineering and Design, vol. 161, 2020, 111934.
# T. Windisch, et al., “Phased array Doppler reflectometry at Wendelstein 7-X”, Review of Scientific Instruments 89, 10H115, 2018.
#M. A. Van Zeeland, et al., “Tests of a two-color interferometer and polarimeter for ITER density measurements”, Plasma Physics and Controlled Fusion, vol. 59, iss. 12, 2017.
#S. B. Korsholm et al., "High power microwave diagnostic for the fusion energy experiment ITER," 2016 41st International Conference on Infrared, Millimeter, and Terahertz waves (IRMMW-THz), Copenhagen, pp. 1-2, 2016.
# F. Arranz et al., "Remote Handling in the Accelerator Systems of DONES," in IEEE Tran. on Plasma Science, vol. 48, no. 6, pp. 1743-1747, June 2020, doi: 10.1109/TPS.2020.2969262.
# G. Miccichè, et al., “The remote handling system of IFMIF-DONES”, Fusion Engineering and Design, vol. 146, Part B, 2019, pp. 2786-2790.
# Q. Xu, et al., “Electrical resistivity measurement of Fe-0.6%Cu alloy irradiated by neutrons at 14- 19 K”, Journal of Nuclear Materials, 481, (2016) 176-180.
# E. Barrera et al., "Implementation of ITER Fast Plant Interlock System Using FPGAs With CompactRIO," in IEEE Trans. on Nuclear Science, vol. 65, no. 2, pp. 796-804, Feb. 2018.
# C. de la Morena, et al., "Fully Digital and White Rabbit-Synchronized Low-Level RF System for LIPAc," IEEE Trans. on Nuclear Science. vol. 65, no. 1, pp. 514 - 522. Jan. 2018.


<hr>
[[LNF:Nationally Funded Projects|Back to list of nationally funded projects]]

[[Category:LNF Nationally Funded Projects]]

LNF: TRANSOPTSTELL. Simulaciones de transporte en plasmas confinados en stellarators y aplicaciones al diseño de dispositivos optimizados (2022-2025)

2025-12-10T10:01:45Z

Elena.delaluna: /* Principales publicaciones */

== LNF - Nationally funded project ==

'''Title''': '''Simulaciones de transporte en plasmas confinados en stellarators y aplicaciones al diseño de dispositivos optimizados '''

'''Reference''': PID2021-123175NB-I00

'''Programme and date''': Plan Estatal de Investigación Científica, Técnica y de Innovación 2021-2023

'''Programme type (Modalidad de proyecto)''': Proyectos de Generación de Conocimiento 2021

'''Area/subarea (Área temática / subárea)''': Ciencias Físicas / Física de partículas y nuclear.

'''Principal Investigator(s)''': [https://orcid.org/0000-0001-8510-1422 José Luis Velasco] e [https://orcid.org/0000-0003-3118-3463 Iván Calvo]

'''Project type''': Proyecto individual / coordinado

'''Start-end dates''': 01/09/2022 - 28/02/2026

'''Financing granted (direct costs)''': 105.000 €

== Description of the project ==

Los conceptos más avanzados para un reactor de fusión basado en confinamiento magnético son el tokamak y el stellarator. En ambos casos, se emplean campos magnéticos con superficies magnéticas toroidales anidadas para confinar una mezcla caliente de electrones e iones de isótopos del hidrógeno. La configuración magnética del tokamak tiene simetría axial, lo cual garantiza un buen confinamiento. Sin embargo, parte de su campo magnético se genera mediante una gran corriente toroidal en el interior del plasma, y esto plantea ciertos problemas. Por un lado, esta corriente puede dar lugar a inestabilidades MHD. Por el otro, la necesidad de producir esta corriente de forma inductiva complica la operación en estado estacionario. Los stellarators no tienen estas desventajas, lo cual los hace atractivos como concepto para futuras centrales eléctricas comerciales: puesto que su campo magnético se genera casi completamente mediante bobinas externas, su operación es intrínsecamente estacionaria, y están libres de inestabilidades generadas por las corrientes del plasma. La contrapartida es que su configuración magnética se vuelve tridimensional, y por tanto son más difíciles de diseñar y construir. Es necesario recurrir a la optimización, es decir, al diseño cuidadoso de las bobinas, de modo que la configuración magnética del stellarator cumpla una serie de criterios y tenga un confinamiento de calidad comparable a la del tokamak. Estos criterios pueden incluir bajo transporte neoclásico (causado por la inhomogeneidad del campo magnético y las colisiones entre partículas) y turbulento, corrientes pequeñas dentro de las superficies magnéticas y buen confinamiento de los iones rápidos. Adicionalmente, la tridimensionalidad de la configuración magnética del stellarator hace necesarios teorías y códigos sofisticados para modelar estos procesos de transporte.

Wendelstein 7-X (W7-X) es el primer stellarator grande diseñado mediante optimización, y sus primeras campañas experimentales han sido un gran éxito. Sin embargo, se diseñó hace décadas y hay margen para la mejora, en particular en relación al confinamiento de los iones rápidos y al transporte turbulento. El siguiente paso en la ruta hacia el stellarator reactor debe ser una máquina que esté suficientemente optimizada con respecto a todos los criterios necesarios. El objetivo de este proyecto es contribuir a ese paso llevando la teoría y simulación del transporte en stellarators al nivel de madurez necesario para mejorar decisivamente la explotación experimental y optimización de stellarators. Específicamente:

- Desarrollaremos códigos numéricos que puedan calcular de forma precisa y eficiente el transporte neoclásico de especies térmicas e iones rápidos y la corriente paralela a las superficies magnéticas. Los compararemos con los códigos estándar de la comunidad stellarator y, cuando sea posible, los validaremos mediante comparación con el experimento.

- Mejoraremos y emplearemos códigos girocinéticos para modelar el transporte turbulento de energía, partículas e impurezas (es decir, especies diferentes a los electrones e isótopos de hidrógeno), y validaremos nuestras predicciones en experimentos en W7-X, LHD y TJ- II.

- Usando estas herramientas, mejoraremos las estrategias de optimización de stellarators y produciremos nuevas configuraciones optimizadas con bobinas factibles para dispositivos de nueva generación.

- Extrapolaremos nuestros descubrimientos a escenarios reactor.


== Main results ==
To be completed at the end of the project (taken from the final report)

== Dissemination of project results (peer-reviewed publications and conference presentations) ==
Enter text here


<hr>
[[LNF:Nationally Funded Projects|Back to list of nationally funded projects]]

[[Category:LNF Nationally Funded Projects]]

LNF: Tecnologías de Litio críticas para IFMIF-DONES

2025-12-10T10:01:14Z

Elena.delaluna: /* Description of the project */

== LNF - Nationally funded project ==

'''Title''': '''Tecnologías de Litio críticas para IFMIF-DONES (Li-CRITEC)'''

'''Reference''': PID2023-150746OB-I00

'''Programme and date''': Convocatoria 2023 - «Proyectos de Generación de Conocimiento»

'''Programme type (Modalidad de proyecto)''': Proyectos investigación orientada

'''Area/subarea (Área temática / subárea)''': Energía y transporte / Energía

'''Principal Investigator(s)''': [https://orcid.org/0000-0001-5407-1611 Joaquin Molla]''' ;''' [https://orcid.org/0000-0001-5407-1611 Francisco Martín-Fuertes]

'''Project type''': Proyecto individual

'''Start-end dates''': 01/09/2024 - 31/08/2028

'''Financing granted (direct costs)''': 160.000 €

== Description of the project ==

IFMIF-DONES is the facility that will be used to irradiate candidate materials for the construction of DEMO and Fusion reactors. Its concept is based on the neutronic radiation produced by the nuclear stripping reaction between 40 MeV deuterons and lithium. The resulting radiation field will produce a damage in materials similar to the one expected in fusion reactors in terms of ratio of gases production (H and He) to displacements. It will be also intense enough to irradiate materials to levels comparable to the conditions foreseen in DEMO. The IFMIF-DONES facility will be composed by three main systems: the accelerator systems, able to produce the 40 Mev deuteron beam, the lithium systems able to provide a liquid lithium target for the deuteron beam, and the irradiation area were the material samples will be irradiated.
<br> The fulfillment of the requirements for the lithium target to be provided by the Li-systems challenges the knowledge on Li technologies. The impurities in lithium may enhance the potential corrosion of Li in the stainless steel pipes. Corrosion increases, in its turn, the amount of impurities in the liquid metal, giving rise to a runaway process. In addition, impurities may be activated due to the presence of radiation fields in the facility, particularly in the target area. Radioactive transmutation products may be also produced due to the neutron irradiation of Li; this is the case of tritium and 7Be, which will circulate with the liquid lithium and have implications for nuclear safety. In addition, impurities can affect the free surface stability of the lithium target. The presence of gases and solid elements might favor nucleation of boiling processes. An Impurity Control System (ICS) is, therefore, required in the plant to monitor and to keep the impurities content below specific limits.
<br> Lithium may also react with gases present in the atmosphere, in particular with water, oxygen and nitrogen. During the normal operation, the Li loop will be operated under inert atmosphere, for which the presence of N, O and water will be controlled. A leakage of lithium out of the loop may evolve into a fire if the inert conditions are partially or totally lost due to an accident scenario. Therefore, the fire risk must be minimized in any situation during the lifetime of the facility.
<br> The systems for controlling and monitoring impurities, traps and sensors, are not completely defined, and research activities on different areas are still required. Also, since the definition of the maximum tolerable values for humidity, oxygen or nitrogen in the inert gas is uncertain, conservative values are presently used. Most of the experience on liquid metals was extrapolated from sodium loops since only a few experiments were done with Li.
<br> This project aims to develop several technologies and requirements related with the use of liquid lithium considered critical for the development of the IFMIF-DONES project, particularly regrading the ICS (including traps and sensors) and safety issues associated to the reactivity of Li with gases in the atmosphere. Four work packages will be developed in parallel:
<br> - '''WP1''': Development of techniques and procedures to measure the impurity content in Li
<br> - '''WP2''': Basic research to understand the behavior of H in the Li-Y-H system
<br> - '''WP3''': Experiments in a small Li loop to study experimentally the trapping and monitoring of impurities
<br> - '''WP4''': Experiments to analyze the reactivity of Li under controlled gas atmospheres
<br>These WP’s will not be executed independently, but they are very much interrelated. WP1 will provide with some support to the other three WP’s. Knowledge generated in WP2 will be very useful to understand the results from WP3. It is also possible that some procedures used in WP2 will be used in WP3 for the determination of H content in Li and Y. Finally, experience gained in WP4 will give some confidence from the safety point of view which will be beneficial for all of the experiments to be performed with liquid lithium.

== Main results ==
To be completed at the end of the project (taken from the final report)

== Dissemination of project results (peer-reviewed publications and conference presentations) ==
Enter text here

== References ==
#Knaster, J et al., The accomplishment of the Engineering Design Activities of IFMIF/EVEDA: The European–Japanese project towards a Li(d,xn) fusion relevant neutron source. Nuclear Fusion 2015, 55 (8), 086003. https://doi.org/10.1088/0029-5515/55/8/086003
#Królas et al.., The IFMIF-DONES fusion oriented neutron source: evolution of the design. Nuclear Fusion 2021, 61 (12), 125002. https://dx.doi.org/10.1088/1741-4326/ac318f
#R. Fernández Saavedra, A. Quejido, Analytical methodology for determination of metallic impurities in lithium, Eurofusion Report, IDM Ref. No: 2QP5VX (2023)
#Hobart EW, Bjork RG. Validity of determining carbon in lithium by measurement of acetylene evolved on hydrolysis. Analytical Chemistry 1967; 39: 202-5
#Sax HI, Steinmetz H. Determination of oxygen in lithium metal. United States, 1958. https://doi.org/10.2172/4298798
#Gahn RF. Determination of oxygen in lithium by the vacuum distillation method. Analytical Chemistry 41 (1969) 1303-6
#H. Yamamoto, M. Murase, S. Izumi, N. Sagawa. “Investigation of Measuring Accuracy of Pluging indicators”. Journal of Nuclear Science and Technology 14:10 (1977) 689-694.
#J.L. Anderson, D.H. Carstens and R.M. Alire “CTR Related tritium research at LASL” Proc. Int. Conf. Radiation Effects and Tritium Technology for Fusion Reactors, Gatlinburg, Tennesse, September 30 – October 3, 1975, CONF-750989, III, 396, J.S. Watson and J.W. Wiffen Eds. (1976)
#P. Hubberstey, P.F. Adams and R.J. Pulham “Hydrogen isotope removal from liquid lithium: use of yttrium sponge as a getter” Proc. Int. Conf. Radiation Effects and Tritium Technology for Fusion Reactors, Gatlinburg, Tennesse, September 30 – October 3, 1975, CONF-750989, III, 270, J.S. Watson and J.W. Wiffen Eds. (1976).
#T. Takeda, A. Ying and M.A. Abdou. “Analysis of tritium extraction from liquid lithium by permeation window and solid gettering processes”. Fusion Engineering and Design 28 (1995) 278-285. DOI: 10.1016/0920-3796(95)90049-7
#C. Bessouet et al., "Characterization of the activation of yttrium-based getter films by electrical measurements and ion-beam analyses," 2019 Symposium on Design, Test, Integration & Packaging of MEMS and MOEMS (DTIP), 2019, pp. 1-4, doi: 10.1109/DTIP.2019.8752932
#M. Kinoshita et al., Experimental study of tritium recovery from liquid lithium by yttrium, Fusion Engineering and Design 81 (2006) 567-571. DOI: j.fusengdes.2005.04.003
#A.B. Hull, O. K. Chopra, B. Loomis, D. L. Smith, Partitioning of Hydrogen in the Vanadium-Lithium-Hydrogen system at elevated temperatures. Eighth Topical Meeting on the Technology of Fusion, Energy, Salt Lake City, Utah, October 9-13, 1988
#Y. Wu, Y. Edao, S. Fukada, H. Nakamura, H. Kondo, Removal rates of hydrogen isotope from liquid Li by HF-treated Y plate, Fusion Engineering and Design, 85, (2010) 1484-1487, DOI: 10.1016/j.fusengdes.2010.04.022
#Y. Hatachi et al., Analysis of hydrogen isotopes absorption between liquid lithium and yttrium under dynamic conditions, Fusion Engineering and Design, 87 (2012) 1457-1460. DOI: j.fusengdes.2012.03.032
#A. Stern, A. Resnik and D. Shaltiel, Thermal desorption spectra of hydrogen in HfV2Hx and ZrV2Hx, Journal of the Less-Common Metals, 1982, 88, 431-440, https://doi.org/10.1016/0022-5088(82)90252-1
#S. J. Hendricks, Modeling and experimental design to characterize permeation and gettering of hydrogen isotopes in fusion materials, PhD Thesis, http://hdl.handle.net/10016/38077 (2023)
#S. J. Hendricks, J. Molla, F. R. Urgorri, E. Carella, Impact of yttrium hydride formation on multi-isotopic hydrogen retention by a getter trap for the DONES lithium loop. Nuclear Fusion 63 (2023) 056012. DOI: 10.1088/1741-4326/acc31a
#T. Sakurai et al., Control of the nitrogen concentration in liquid lithium by the hot trap method, Journal of Nuclear Materials 307–311, Part 2 (2002) 1380-1385 DOI: 10.1016/S0022-3115(02)01125-X
#D. Martelli, G. Barone, M. Tarantino, M. Utili, Design of a new experimental loop and of a coolant purifying system for corrosion experiments of EUROFER samples in flowing PbLi environment, Fusion Engineering and Design 124 (2017) Pages 1144-1149, ISSN 0920-3796, https://doi.org/10.1016/j.fusengdes.2017.01.054
#B.R. Grundy “Experimental characterization of sodium cold traps and modelling of their behaviour” Proc. Int. Conf. on Liq. Met. Tech. in En. Prod., Champion (1976) 650
#C. C. McPheeters, MASS TRANSFER OF OXYGEN IN SODIUM COLD TRAPS, Technical Report UCA (USA), doi:10.2172/4505711 (1968)
#B C Goplen, J C, Biery, and C C. McPheeters, NUMERICAL SIMULATION OF A COLD TRAP FOR SODIUM PURIFICATION, Technical Report UCA (USA). doi: 10.2172/4130823.(1970)
#S. D. Clinton and J. S. Watson, the solubility of tritium in yttrium at temperatures from 250 to 400 “C. Journal of the Less-Common Metals, 66 (1979) 51 - 57
#H. Nakamura, M. Ida, M. Sugimoto, T. Yutani & H. Takeuchi (2002) Removal and Control of Tritium in Lithium Target for International Fusion Materials Irradiation Facility (IFMIF), Fusion Science and Technology, 41:3P2 (2002) 845--849, DOI: 10.13182/FST02-A22704
#Favuzza, P.; Antonelli, A.; Furukawa, T.; Groeschel, F.; Hedinger, R.; Higashi, T.; Hirakawa, Y.; Iijima, M.; Ito, Y.; Kanemura, T.; et al. Round Robin test for the determination of nitrogen concentration in solid lithium. Fusion Eng. Des. 107 (2016) 13–24. DOI: 10.1016/j.fusengdes.2016.03.026
# Marinari, R.; Favuzza, P.; Bernardi, D.; Nitti, F.S.; Di Piazza, I. CFD Optimization of the Resistivity Meter for the IFMIF-DONES Facility. Energies 2021, 14, 2543. DOI: 10.3390/en14092543
# A. Aiello, A. Tincani, P. Favuzza, F.S. Nitti 1, L. Sansone, G. Miccichè, M. Muzzarelli, G. Fasano, P. Agostini, “Lifus (lithium for fusion) 6 loop design and construction”, Fusion Engineering and Design 88 (2013) 769-773
# A.Ferreira da Silva, J. Pernot, S. Contreras, B. Sernelius, C. Persson, J. Camassel, “electrical resistivity and metal-nometal transition in n-type doped 4h-SiC” Phys. Rev. B 74 (2006) 24 doi.org/10.1103/PhysRevB.74.245201
# H. Kondo et al., Completion of IFMIF/EVEDA lithium test loop construction, Fusion Engineering and Design 87 (2012) 418-422, ISSN 0920-3796, https://doi.org/10.1016/j.fusengdes.2011.11.011.
# P. Favuzza, A. Antonelli, M. Cuzzani, G. Fasano, S. Mannori, Final Validation Report of the Lifus 6 Purification System, Deliverable: LF 4.5.2 IFMIF/EVEDA Report DMS Ref. No: BA_D_23PVKK (2016)
# Y. Ito, M. Hirano, H. Tanaka, E. Wakai, S. Fukada, A. Suzuki, T. Higashi, J. Yagi, Validation Report of Purification System by Fundamental Experiments in Laboratory Scale at the Japanese Universities, Deliverable LF4.3.2 IFMIF/EVEDA Project, IFMIF/EVEDA Report DMS Ref. No: BA_D_248V9J (2015)
# Procurement Arrangement LF06-2 JA for the Fusion Neutron Source Target Research & Development 2021-2025 (QST Contribution) for the IFMIF/EVEDA Project during BA phase II, IFMIF/EVEDA Report DMS Ref. No: BA_D_27RXT8 (2021)
# Oyaidzu Makoto, Design of the 1:10 pilot purification plant including the pilot plugging monitor, IFMIF/EVEDA Report DMS Ref. No: BA_D_ 28Z5AG (2022)
# P. Favuzza, Task Spec. 2022 ENEA contribution to Lithium Systems area, Eurofusion Report, IDM Ref. No: EFDA_D_2PTZUX (2022)
# S. Gordeev, Task Spec. 2022 KIT contribution to Lithium Systems area, Eurofusion Report, IDM Ref. No: EFDA_D_2PU452 (2022)
# Creffrey, G.K.; Down, M.G.; Pulham, R.J. “Electrical Resistivity of Liquid and Solid Lithium”. J. Chem. Soc. Dalton Trans. 21 (1974) 2325–2329 https://doi.org/10.1039/DT9740002325
# Hubberstey, P., “Dissolved nitrogen in liquid‐lithium a problem in fusion reactor chemistry”, Liquid metal engineering and technology. 3 v. Proc. 3. Int. conference held in Oxford on 9‐13 (1984) BNES 1984 v.2, 85‐91
# Hubberstey, P.; Roberts, P.G. “Corrosion chemistry of vanadium in liquid lithium containing dissolved nitrogen”. J. Nucl. Mater 1555157 (1988) 694–697 doi:10.1016/0022-3115(88)90397-2
# F. Barbier, “Continuous monitoring and adjusment of the lithium content in liquid Pb Li alloys: assessment of and electrical resistivity meter in a loop system”. Fusion Engineering and Design, 36 (1997) 299-308 https://doi.org/10.1016/S0920-3796(96)00697-7
# D.W. Jeppson, Interactions of liquid lithium with various atmospheres, concretes, and insulating materials; and filtration of lithium aerosols, 1979. https://doi.org/10.2172/6122331.
# D.W. Jeppson, Scoping studies: behavior and control of lithium and lithium aerosols, 1982. https://doi.org/10.2172/5182052.
# D.W. Jeppson, Results and code prediction comparisons of lithium-air reaction and aerosol behavior tests, United States, 1986. https://inis.iaea.org/search/18000591.
# D.S. Barnett, T.K. Gil, M.S. Kazimi, Lithium-Mixed Gas Reactions, Fusion Technology 15 (1989) 967–972. https://doi.org/10.13182/FST89-A39818.
# S.J. Piet, D.W. Jeppson, L.D. Muhlestein, M.S. Kazimi, M.L. Corradini, Liquid metal chemical reaction safety in fusion facilities, Fus. Engin. and Design 5 (1987) 273–298. https://doi.org/10.1016/S0920-3796(87)90032-9.
# R.A. Rhein, Lithium Combustion: A Review, Defense Technical Information Center, Fort Belvoir, VA, 1990. https://doi.org/10.21236/ADA238154.
# M. Schiemann, J. Bergthorson, P. Fischer, V. Scherer, D.Taroata, G. Schmid, A review on lithium combustion, Applied Energy 162 (2016) 948–965. https://doi.org/10.1016/j.apenergy.2015.10.172.
# G. D’Ovidio, F. Martín-Fuertes, D. Alegre, J.C. Marugán, A. Pitigoi, J. Sierra, J. Molla, CIEMAT experimental proposal on lithium ignition in support of DONES licensing (LiFIRE facility), Nuclear Materials and Energy 31 (2022) 101177. https://doi.org/10.1016/j.nme.2022.101177.
# C.C. McPheeters, J.C. Biery. “The Dynamic Characteristics of Plugging Indicator for Sodium”. Nuclear Applications 6:6 (1969) 573-581. DOI: https://doi.org/10.13182/NT69-A28287
# Feron, D. (1982). Plugging Indicator - Measurement of Low Impurity Concentrations at a Constant Orifice Temperature. In: Borgstedt, H.U. (eds) Material Behavior and Physical Chemistry in Liquid Metal Systems. Springer, Boston, MA. pp.89-96. DOI: https://doi.org/10.1007/978-1-4684-8366-6_9
# N. Holstein, W. Krauss, J. Konys, F.S. Nitti “Development of an electrochemical sensor for hydrogen detection in liquid lithium for IFMIF-DONES” Fusion Engineering and Design 146 (2019) Pages 1441-1445 https://doi.org/10.1016/j.fusengdes.2019.02.100
# N. Holstein, W. Krauss, F.S. Nitti “Electrochemical hydrogen detection in DONES loop materials” Nuclear Materials and Energy 31 (2022) 101192 DOI: https://doi.org/10.1016/j.nme.2022.101192
# M. Schiemann, J. Bergthorson, P. Fischer, V. Scherer, D. Taroata, G. Schmid, A review on lithium combustion, Applied Energy 162 (2016) 948–965. https://doi.org/10.1016/j.apenergy.2015.10.172.
# J. Peng, H. Li, L. Chen, F. Wu, Application of Liquid Metal Electrodes in Electrochemical Energy Storage, Precision Chemistry 1 (2023) 452–467. https://doi.org/10.1021/prechem.3c00030.


<hr>
[[LNF:Nationally Funded Projects|Back to list of nationally funded projects]]

[[Category:LNF Nationally Funded Projects]]

LNF: STRANAI: STRAtegic network for Nuclear fusion research acceleration through Artificial Intelligence techniques

2025-12-10T10:00:39Z

Elena.delaluna: /* Description of the project */

== LNF - Nationally funded project ==

'''Title''': '''STRANAI: STRAtegic network for Nuclear fusion research acceleration through Artificial Intelligence techniques'''

'''Reference''': RED2024-153593-E

'''Programme and date''': Proyectos de 2 Años

'''Programme type (Modalidad de proyecto)''': Red de investigación

'''Area/subarea (Área temática / subárea)''': Energía / Ciencias físicas

'''Principal Investigator(s)''': [https://orcid.org/0000-0002-5676-9631 Giuseppe Rattá Gutiérrez]

'''Project type''': Proyecto coordinado

'''Start-end dates''': 01/05/2025 - 31/04/2027

'''Financing granted (direct costs)''': 65000 €

== Description of the project ==

STRANAI is a national strategic network coordinated by the Laboratorio Nacional de Fusión (CIEMAT) that connects eight leading Spanish research groups in the fields of artificial intelligence, plasma physics, and fusion technology. The goal is to promote national and international collaboration, particularly within the framework of EUROfusion, through the development and application of AI tools to critical challenges in magnetic confinement fusion.

The network focuses on six research lines: (1) detection of physical events from videos and images, (2) automation of turbulence analysis via Doppler reflectometry, (3) development of explainable and physics-informed AI models, (4) creation of shared data and code repositories, (5) plasma control and operational limits, and (6) disruption prediction and mitigation.

Participating groups include CIEMAT-LNF, BSC, UNED, CETA-CIEMAT, IFMIF-DONES, UPO, CAR (CSIC-UPM), and the PSFT group at the University of Seville. The network benefits from access to major international facilities and HPC resources. STRANAI aims to develop transferable tools and methodologies for devices such as ITER, DEMO, SMART, and IFMIF-DONES.

== Main results ==
To be completed at the end of the project (taken from the final report)

== Dissemination of project results (peer-reviewed publications and conference presentations) ==
Enter text here

== References ==
<references />


<hr>
[[LNF:Nationally Funded Projects|Back to list of nationally funded projects]]

[[Category:LNF Nationally Funded Projects]]

LNF: Producción industrial Pb-15.7Li

2025-12-10T10:00:01Z

Elena.delaluna:

== LNF - Public Private Partnership ==

'''Title''': '''PRODUCCIÓN INDUSTRIAL DE LA ALEACIÓN EUTÉCTICA DE LITIO-PLOMO- EUTECTICS®'''

'''Reference''': CPP2021-008665

'''Programme and date''': PROGRAMA ESTATAL PARA IMPULSAR LA INVESTIGACIÓN
CIENTÍFICO-TÉCNICA Y SU TRANSFERENCIA, DEL PLAN ESTATAL DE INVESTIGACIÓN CIENTÍFICA, TÉCNICA
Y DE INNOVACIÓN 2021-2023, EN EL MARCO DEL PLAN DE RECUPERACIÓN, TRANSFORMACIÓN Y
RESILIENCIA

'''Programme type (Modalidad de proyecto)''': COLABORACIÓN PÚBLICO-PRIVADA

'''Principal Investigator(s)''': Belit Garcinuño (CIEMAT)

'''Project type''': Proyecto coordinado

'''Start-end dates''': 2022 - 2025

'''Financing granted (direct costs)''': 599.549,80 €

== Description of the project ==

The eutectic alloy of lithium and lead [15,7(2) % at Li with exact composition yet to be certified] is a functional tritium regenerating material and "base of design" for fusion reactors under construction, ITER and future (DEMO).
ITER will require tons of the alloy as material in the systems (TBM, Test Blanket Modules) together with tons of the material for the ongoing experimental programs around the world: in the EU, Japan, India, the United States , Korea and China. The material was born at the end of the 70s as a proposal for laboratory material [D.K. Sze (INEL, United States), v. Coen (JRC Ispra, EU)] on a laboratory scale far from the quality standards of a nuclear material.
Industrial and development returns in the coming years in the EU alone are estimated at around €40 million, depending on certain programmatic variables and the demonstration of its manufacture under Nuclear Material standards (IAEA Standards, RCC_MR Codes, ISO, ASTM,...) represents a technological challenge of the first order and is, without a doubt, an enormous opportunity for potential contribution and industrial returns from Spanish companies to ITER. Producing the alloy without quality assurance is not high-tech and some well-known laboratories in the world do it. Producing the alloy with the required quality assurance of a nuclear material and whose characteristics affect the safety of the reactor, is a true high-tech challenge in aspects related with: (1) the final certification of the title in lithium, (2) the homogeneity without segregation of lithium at sub millimetric scales, (3) the extreme control of impurities and (4) the demands of certified characterization of its functional database under standards as nuclear material. The production of the eutectic alloy for its final use in ITER (N, TT, IN phases of TBMs) requires the capacity to produce significant quantities of 6Li and the demonstration of an industrially scalable and quality-assured alloying technique. Our Project aims to demonstrate the manufacturing capacity of the material with the complete Quality Assurance of the eutectic as nuclear material from an industrially scalable technique to meet the assessed supply demands in the EU and in other ITER Programs.
The main challenge of the project consists of the experimental demonstration of an industrially scalable production technique of the eutectic alloy of Lithium-Lead (Pb-15.7(2)Li); along with the enrichment capacity in 6Li, all under Nuclear Material Standards.
Its 4 main OBJECTIVES: (1) Establishment of the Standard (UNE) of Quality of the material in its production, handling and qualification. Establishment of a national network of characterization and qualification laboratories. (2) Experimental demonstration of a scalable Li(6) isotopic separation technique (1 kg); (3) Experimental demonstration of a Li-Pb mixing technique under quality requirements; industrially scalable (1 Tn); (4) Key actions towards industrialization in the production of lots of Pb-15.76Li.
To achieve the Objectives of the Project, the activities are structured in the realization of 22 specific tasks of public-private collaboration between our Company FUS_ALIANZ and the Chemical Institute of Sarrià, the Rovira i Virgili University, CIEMAT, IDONIAL and CIEMAT. Nominated subcontractors are UNED, IPUL (Latvia) and Riera Nadeu S.A.

== Main results ==
To be completed at the end of the project (taken from the final report)

== Dissemination of project results (peer-reviewed publications and conference presentations) ==
Enter text here

== References ==
<references />
[1] Belit Garcinuño, Rocío Fernández-Saavedra, Teresa Hernández, Alberto Quejido, David Rapisarda; “Establishing technical specifications for PbLi eutectic alloy analysis and its relevance in fusion applications”; NUCLEAR MATERIALS AND ENERGY (2022) https://doi.org/10.1016/j.nme.2022.101146

[2] M. I. Barrena et al., “Obtención de aleaciones eutécticas PbLi mediante procesos de fusion”, Rev. Metal. 48-6 (2012) 437-444

[3] R. Fernández-Saavedra, B. Garcinuño, M. Gómez-Mancebo, F. Borlaf, A. Cardona, M. González-Macías, M. Clavero, J. Patiño, J. Navas, T. Hernández, J. García-Ferreño, J. Artímez, J. Abellà, S. Colominas, J. Herranz, L. Sedano, D. Rapisarda, A. Quejido, Comparative study of preparation methods and properties of lead-lithium eutectic for fusion technology. 15th International Symposium on Fusion Nuclear Technologies (15-ISFNT) – Poster presentation PS4-61. Las Palmas de Gran Canaria (España) 10-15 septiembre 2023

[4] L. Sedano, M. Guasch, J. Abellà , S. Colominas, F. Medina, J.M. Artimez, D. Rapisarda, B. Garcinuño, R. Fernandez, F. Ogando, L. Buligin, Producción industrial de la aleación eutéctica de litio-plomo enriquecida en 6Li (Pb-15.76Li): material estratégico en Tecnología de Fusión. 47ª Reunión Anual de la Sociedad Nuclear Española, Poster 40_05. Cartagena (España) 26-30 septiembre 2022

[5] B. Garcinuño, R. Fernández-Saavedra, T. Hernández, A. Quejido, D. Rapisarda, Protocol for PbLi eutectic alloy analysis and its relevance in fusion applications. 20th International Conference on Fusion Reactor Materials (20-ICFRM) – Poster T_PS_2_C-79. Virtual meeting, 24-29 octubre 2021

[[File: CPP.png]]


<hr>
[[LNF:Nationally Funded Projects|Back to list of nationally funded projects]]

[[Category:LNF Nationally Funded Projects]]

LNF: Producción industrial Pb-15.7Li

2025-12-10T09:59:40Z

Elena.delaluna: /* Description of the project */

== LNF - Public Private Partnership ==

'''Title''': '''PRODUCCIÓN INDUSTRIAL DE LA ALEACIÓN EUTÉCTICA DE LITIO-PLOMO- EUTECTICS®'''

'''Reference''': CPP2021-008665

'''Programme and date''': PROGRAMA ESTATAL PARA IMPULSAR LA INVESTIGACIÓN
CIENTÍFICO-TÉCNICA Y SU TRANSFERENCIA, DEL PLAN ESTATAL DE INVESTIGACIÓN CIENTÍFICA, TÉCNICA
Y DE INNOVACIÓN 2021-2023, EN EL MARCO DEL PLAN DE RECUPERACIÓN, TRANSFORMACIÓN Y
RESILIENCIA

'''Programme type (Modalidad de proyecto)''': COLABORACIÓN PÚBLICO-PRIVADA

'''Principal Investigator(s)''': Belit Garcinuño (CIEMAT)

'''Project type''': Proyecto coordinado

'''Start-end dates''': 2022 - 2025

'''Financing granted (direct costs)''': 599.549,80 €

== Description of the project ==

The eutectic alloy of lithium and lead [15,7(2) % at Li with exact composition yet to be certified] is a functional tritium regenerating material and "base of design" for fusion reactors under construction, ITER and future (DEMO).
ITER will require tons of the alloy as material in the systems (TBM, Test Blanket Modules) together with tons of the material for the ongoing experimental programs around the world: in the EU, Japan, India, the United States , Korea and China. The material was born at the end of the 70s as a proposal for laboratory material [D.K. Sze (INEL, United States), v. Coen (JRC Ispra, EU)] on a laboratory scale far from the quality standards of a nuclear material.
Industrial and development returns in the coming years in the EU alone are estimated at around €40 million, depending on certain programmatic variables and the demonstration of its manufacture under Nuclear Material standards (IAEA Standards, RCC_MR Codes, ISO, ASTM,...) represents a technological challenge of the first order and is, without a doubt, an enormous opportunity for potential contribution and industrial returns from Spanish companies to ITER. Producing the alloy without quality assurance is not high-tech and some well-known laboratories in the world do it. Producing the alloy with the required quality assurance of a nuclear material and whose characteristics affect the safety of the reactor, is a true high-tech challenge in aspects related with: (1) the final certification of the title in lithium, (2) the homogeneity without segregation of lithium at sub millimetric scales, (3) the extreme control of impurities and (4) the demands of certified characterization of its functional database under standards as nuclear material. The production of the eutectic alloy for its final use in ITER (N, TT, IN phases of TBMs) requires the capacity to produce significant quantities of 6Li and the demonstration of an industrially scalable and quality-assured alloying technique. Our Project aims to demonstrate the manufacturing capacity of the material with the complete Quality Assurance of the eutectic as nuclear material from an industrially scalable technique to meet the assessed supply demands in the EU and in other ITER Programs.
The main challenge of the project consists of the experimental demonstration of an industrially scalable production technique of the eutectic alloy of Lithium-Lead (Pb-15.7(2)Li); along with the enrichment capacity in 6Li, all under Nuclear Material Standards.
Its 4 main OBJECTIVES: (1) Establishment of the Standard (UNE) of Quality of the material in its production, handling and qualification. Establishment of a national network of characterization and qualification laboratories. (2) Experimental demonstration of a scalable Li(6) isotopic separation technique (1 kg); (3) Experimental demonstration of a Li-Pb mixing technique under quality requirements; industrially scalable (1 Tn); (4) Key actions towards industrialization in the production of lots of Pb-15.76Li.
To achieve the Objectives of the Project, the activities are structured in the realization of 22 specific tasks of public-private collaboration between our Company FUS_ALIANZ and the Chemical Institute of Sarrià, the Rovira i Virgili University, CIEMAT, IDONIAL and CIEMAT. Nominated subcontractors are UNED, IPUL (Latvia) and Riera Nadeu S.A.



== Main results ==
To be completed at the end of the project (taken from the final report)

== Dissemination of project results (peer-reviewed publications and conference presentations) ==
Enter text here

== References ==
<references />
[1] Belit Garcinuño, Rocío Fernández-Saavedra, Teresa Hernández, Alberto Quejido, David Rapisarda; “Establishing technical specifications for PbLi eutectic alloy analysis and its relevance in fusion applications”; NUCLEAR MATERIALS AND ENERGY (2022) https://doi.org/10.1016/j.nme.2022.101146

[2] M. I. Barrena et al., “Obtención de aleaciones eutécticas PbLi mediante procesos de fusion”, Rev. Metal. 48-6 (2012) 437-444

[3] R. Fernández-Saavedra, B. Garcinuño, M. Gómez-Mancebo, F. Borlaf, A. Cardona, M. González-Macías, M. Clavero, J. Patiño, J. Navas, T. Hernández, J. García-Ferreño, J. Artímez, J. Abellà, S. Colominas, J. Herranz, L. Sedano, D. Rapisarda, A. Quejido, Comparative study of preparation methods and properties of lead-lithium eutectic for fusion technology. 15th International Symposium on Fusion Nuclear Technologies (15-ISFNT) – Poster presentation PS4-61. Las Palmas de Gran Canaria (España) 10-15 septiembre 2023

[4] L. Sedano, M. Guasch, J. Abellà , S. Colominas, F. Medina, J.M. Artimez, D. Rapisarda, B. Garcinuño, R. Fernandez, F. Ogando, L. Buligin, Producción industrial de la aleación eutéctica de litio-plomo enriquecida en 6Li (Pb-15.76Li): material estratégico en Tecnología de Fusión. 47ª Reunión Anual de la Sociedad Nuclear Española, Poster 40_05. Cartagena (España) 26-30 septiembre 2022

[5] B. Garcinuño, R. Fernández-Saavedra, T. Hernández, A. Quejido, D. Rapisarda, Protocol for PbLi eutectic alloy analysis and its relevance in fusion applications. 20th International Conference on Fusion Reactor Materials (20-ICFRM) – Poster T_PS_2_C-79. Virtual meeting, 24-29 octubre 2021

[[File: CPP.png]]


<hr>
[[LNF:Nationally Funded Projects|Back to list of nationally funded projects]]

[[Category:LNF Nationally Funded Projects]]

LNF: LIMPLASH, Liquid Metal Plasma Shields as new generation power exhaust solutions for magnetic fusion devices (2025-2028)

2025-12-10T09:58:44Z

Elena.delaluna: /* Description of the project */

== LNF - Nationally funded project ==

'''Title''': '''LIMPLASH, Liquid Metal Plasma Shields as new generation power exhaust solutions for magnetic fusion devices'''

'''Reference''': PID2024-161233OA-I00

'''Programme and date''': Proyectos de Generación de Conocimiento, convocatoria 2024

'''Programme type (Modalidad de proyecto)''': Tipo A

'''Area/subarea (Área temática / subárea)''': Ciencias Físicas/Física de partículas y nuclear

'''Principal Investigator(s)''': [https://orcid.org/0000-0003-2620-9825 Alfonso de Castro]

'''Project type''': Proyecto individual

'''Start-end dates''': 01/09/2025 - 31/08/2028

'''Financing granted (direct costs)''': 40625 €

== Description of the project ==

The development of new baseline, large scale, 24/7 availability, and carbon-free energy sources is paramount to reduce the global dependence on
fossil fuels and its effects on biosphere modification, questions that are accelerating the climate change and nature degradation trends. Under such
scenario, nuclear fusion is seen as hopeful option with intrinsic 24/7 availability and tremendously high energy density potential. It plans to use raw
materials inexhaustible in the human time scale and not geographically concentrated, being the power generation theoretically free of long-lived
radioactive wastes and inherently safe (no runaway reaction or explosions unlike fission energy). Within the magnetic fusion research, one of the key
remaining issues for its development is the performance and resilience of the elements in unavoidable contact with the fusion plasma, the so-called
Plasma Facing Components (PFCs) that will need to handle extreme heat fluxes (steady state 10 MW/m2 and transients of GW/m2 range in ms
timescales). As the physics/technical feasibility of conventional PFC solutions (based on solid tungsten elements) and the related power exhaust
scenario does not appear guaranteed or straightforward [1], active research on novel, advanced and alternative Liquid Metal (LM) PFCs has emerged
mainly using Tin (Sn), lithium (Li) and their alloys (SnLi) as candidates [2]. Amid a fusion-relevant heat load irradiation scenario, LM surfaces can act as a
sacrifice interface by favoring the creation of LM vapor/plasma clouds in front of it. The process is generally denominated vapor shielding [3] and offers an
alternative and novel approach to the power exhaust problem. In this way, the power load fraction that utterly reaches the PFC substrate
surface/structure can be decreased due to the volumetric dissipation that takes place in the LM cloud, thus allowing to enhance the total power exhaust
capabilities beyond single conductive transfer that characterizes tungsten PFCs (additional vaporization, radiation and convection channels in the LM
layer and vapor/plasma cloud). The experimental study and data analysis work on the fundamental characterization of LM enriched plasmoids and their
associated thermal shielding regimes are the main objective of this proposal. Such plasmoids will be experimentally generated by the irradiation of
prototypic LM targets with fusion relevant heat fluxes by means of both particle beam and high power laser irradiation [4]. This research on LM PFCs and
their associated plasmoids attempts to explore an alternative solution that can help to handle the extreme power exhaust scenario expected in future
magnetic fusion devices. The activities aim to answer scientific fundamental questions and generate basic knowledge to significantly advance in the
comprehension and understanding of LM plasmoids capable of contributing to the major task of power exhaust in future fusion devices. This proposal
pursues to continue a recently open research line with Sn prototypes (in which a novel LM embedded Langmuir Probe configuration has been developed [5] for
LM plasmoid diagnosis), fully extend it to SnLi alloy targets and develop technological upgrades to eventually apply this research to pure
lithium PFCs. The proposed works will be conducted in collaboration with world class, leading institutions in the fields of nuclear fusion and LM PFCs
both in Europe (DiFFER, Netherlands) and USA (University of Illinois at Urbana-Champaign).



== Main results ==
To be completed at the end of the project (taken from the final report)

== Dissemination of project results (peer-reviewed publications and conference presentations) ==
Enter text here

== References ==

[1] J. Linke, J. Du, T. Loewenhoff et al., “Challenges for plasma-facing components in nuclear fusion”, Matter Radiat.
Extrem. 4 (2019) 056201.

[2] R. E. Nygren and F. L. Tabares, “Liquid surfaces for fusion plasma facing components - A critical review. Part I:
Physics and PSI”, Nucl. Mater. Energy 9 (2016) 6.

[3] G. G. van Eden T. W. Morgan et al., “Oscillatory vapour shielding of liquid metal walls in nuclear fusion devices”,
Nat. Commun. 8 (2017) 192

[4] A. De Castro, et al. “Physics and technology research for liquid-metal divertor development, focused on a tin-
Capillary Porous System solution, at the OLMAT high heat-flux facility”, J. Fus. Ener., 42 (2023) 45

[5] A. de Castro, M. Reji, D. Tafalla et al., “Dynamics of tin plasmoids and vapor shielding onset from a liquid
metal CPS target using ITER intra-ELM energy-range H0/H+ beams”, Nucl. Fusion, 65 (2025) 056034


<hr>
[[LNF:Nationally Funded Projects|Back to list of nationally funded projects]]

[[Category:LNF Nationally Funded Projects]]

LNF: Fusion LiqUid meTals HYdrogen ExtRaction (Fusion LUTHYER)

2025-12-10T09:58:24Z

Elena.delaluna:

== LNF - Nationally funded project ==

'''Title''': '''Fusion LiqUid meTals HYdrogen ExtRaction (Fusion LUTHYER)'''

'''Reference''': PID2022-140644OA-I00

'''Programme and date''': Proyectos de Generación de Conocimiento, convocatoria 2022

'''Programme type (Modalidad de proyecto)''': Tipo A

'''Area/subarea (Área temática / subárea)''': Energía y transporte

'''Principal Investigator(s)''': Belit Garcinuño [https://orcid.org/0000-0003-3849-3122]

'''Project type''': Proyecto individual

'''Start-end dates''': 01/09/2023 - 01/09/2026

'''Financing granted (direct costs)''': 100.000,00 €

'''Website''': https://agenda.ciemat.es/event/4910/

== Description of the project ==

This proposal aims to address key activities related to liquid metals in the international Fusion scientific program, through dedicated experimental activities supported by theoretical simulations. One of the main operational objectives of a fusion reactor is to ensure tritium self-sufficiency, but techniques currently proposed for tritium extraction have not been fully validated, both from the numerical and experimental points of view. The experiments proposed in Fusion LUTHYER are focused on the validation of a technique for tritium extraction from PbLi based on Permeation Against Vacuum (PAV).The backbone of the project is devoted to the experimental expoliation of the PbLi circuit CLIPPER, already in operation at LML. CLIPPER is an experimental facility designed to provide a flexible operational scenario for the validation of the Permeation Against Vacuum (PAV) technique for tritium extraction from PbLi. This technology can be applied by means of tritium permeation through a membrane or by the direct exposition of the liquid metal to the vacuum.
Fusion LUTHYER is organized in four blocks:

- ''Extraction of light ions from liquid metals''. Tritium extraction from the liquid metal compiles a critical unsolved issue, since the presence of H-isotopes directly impairs safety and maintenance of the installation. Different extraction techniques have been proposed along the years, and of them the permeation against vacuum (PAV) has been selected as the most suitable for DEMO. To perform this kind of experiments at laboratory scale, hydrogen isotopes cannot be generated in the liquid metal through nuclear reactions. Therefore, gas injection systems and concentration sensors are needed, and the support of modeling and chemical characterization activities is a key aspect.

- ''Detection of light ions in liquid metals''. There is a need to monitor the content of H, and more specifically the content of tritium, during the operation of the experiment. The reference solution for monitoring is the chemical analysis off-beam by means of PbLi specimens extracted from the loop. An on-line monitoring is foreseen by the development of two sensors for hydrogen isotopes; the first one is based on the permeation against vacuum technology; the second one, based on electrochemical measurements.

- ''Modelling activities in support of the experiments''. The modelling is an essential tool for the definition of the experiments. It compiles all physic-chemical processes with the operational parameters of the CLIPPER loop to obtain results in the limit of detection of the equipment and comparable to what is expected. One of the most attractive principles of nuclear fusion is that the radioactive waste produced in a commercial reactor should be classified as Low-Level Waste (LLW) within 100 years after the end of life (EOL).

-'' Analysis activities in support of the experiments''. A proper characterization of the PbLi materials is fundamental not only for the development of tritium efficient extraction methods, but also for tritium inventory control.

As a summary, the activities proposed in the framework of the Fusion LUTHYER project include a set of experimental and modeling tasks focused on some challenges in the liquid metals technology (PbLi) for its application to critical systems in the path to a DEMO reactor, as the tritium extraction system.

== Main results ==
To be completed at the end of the project (taken from the final report)

== Dissemination of project results (peer-reviewed publications and conference presentations) ==
Enter text here



== References ==
# B. Garcinuño et al., “The CIEMAT LiPb Loop Permeation Experiment”, Fusion Eng. Des. 146 (2019) 1228-1232
# B. Garcinuño et al., “The Tritium Extraction and Removal System for the DCLL-DEMO fusion reactor”, Nucl. Fusion 58 (2018) 095002
# B. Garcinuño et al., “Design and fabrication of a Permeator Against Vacuum prototype for small scale testing at Lead-Lithium facility”, Fusion Eng. Des. 124 (2017) 871-875
# F.R. Urgorri et al., "Theoretical evaluation of the tritium extraction from liquid metal flows through a free surface and through a permeable membrane" Nuclear Fusion 63 (2023) 63 046025
# F.R. Urgorri et al., A “Tritium transport modeling at system level for the EUROfusion dual coolant lithium-lead breeding blanket”,Nucl. Fusion, 57 (2017) 116045
# B. Garcinuño et al., “Development of an on-line sensor for hydrogen isotopes monitoring in flowing lithium at DONES” Fusion Eng. Des. 161 (2020) 112010
# B. Garcinuño et al., “Establishing technical specifications for PbLi eutectic alloy analysis and its relevance in fusion applications”, Nucl. Mater. Energy 30, pp. 101146 (2022)
# M. Malo et al., "Experimental refutation of the deuterium permeability in vanadium, niobium and tantalum" Fusion Engineering and Design 146-A (2019) 224-227
# I. Peñalva et al., "Hydrogen Transport Model in Eutectic PbLi for Data Evaluation in an Absorption-Desorption Experimental Facility" Fusion Science and Technology (2024) 80(3–4) 596–606
# M. Malo et al., "Experimental Determination of Hydrogen Isotope Transport Parameters in Vanadium" Membranes 2022, 12(6), 579
# D. Rapisarda et al., “The European Dual Coolant Lithium Lead breeding blanket for DEMO: status and perspectives”, Nucl. Fusion 61 (2021) 1150011
# I. Palermo et al., “Tritium production assessment for the DCLL EUROfusion DEMO”, Nucl. Fusion 56 (2016) 104001
# I. Palermo et al., “Radiological impact mitigation of waste coming from the European fusion reactor DEMO with DCLL breeding blanket” Fusion Eng. Des. 124 (2017) 1257-1262
# G. A. Spagnuolo et al., "Integration issues on tritium management of the European DEMO Breeding Blanket and ancillary systems" Fusion Engineering and Design 171 (2021) 112573
# M. Utili et al., "Design and Integration of the WCLL Tritium Extraction and Removal System into the European DEMO Tokamak Reactor" Energies 2023, 16(13), 5231

[[File:File.png]]


<hr>
[[LNF:Nationally Funded Projects|Back to list of nationally funded projects]]

[[Category:LNF Nationally Funded Projects]]

LNF: Fusion LiqUid meTals HYdrogen ExtRaction (Fusion LUTHYER)

2025-12-10T09:57:38Z

Elena.delaluna: /* Description of the project */

== LNF - Nationally funded project ==

'''Title''': '''Fusion LiqUid meTals HYdrogen ExtRaction (Fusion LUTHYER)'''

'''Reference''': PID2022-140644OA-I00

'''Programme and date''': Proyectos de Generación de Conocimiento, convocatoria 2022

'''Programme type (Modalidad de proyecto)''': Tipo A

'''Area/subarea (Área temática / subárea)''': Energía y transporte

'''Principal Investigator(s)''': Belit Garcinuño [https://orcid.org/0000-0003-3849-3122]

'''Project type''': Proyecto individual

'''Start-end dates''': 01/09/2023 - 01/09/2026

'''Financing granted (direct costs)''': 100.000,00 €

'''Website''': https://agenda.ciemat.es/event/4910/

== Description of the project ==

This proposal aims to address key activities related to liquid metals in the international Fusion scientific program, through dedicated experimental activities supported by theoretical simulations. One of the main operational objectives of a fusion reactor is to ensure tritium self-sufficiency, but techniques currently proposed for tritium extraction have not been fully validated, both from the numerical and experimental points of view. The experiments proposed in Fusion LUTHYER are focused on the validation of a technique for tritium extraction from PbLi based on Permeation Against Vacuum (PAV).The backbone of the project is devoted to the experimental expoliation of the PbLi circuit CLIPPER, already in operation at LML. CLIPPER is an experimental facility designed to provide a flexible operational scenario for the validation of the Permeation Against Vacuum (PAV) technique for tritium extraction from PbLi. This technology can be applied by means of tritium permeation through a membrane or by the direct exposition of the liquid metal to the vacuum.
Fusion LUTHYER is organized in four blocks:

- ''Extraction of light ions from liquid metals''. Tritium extraction from the liquid metal compiles a critical unsolved issue, since the presence of H-isotopes directly impairs safety and maintenance of the installation. Different extraction techniques have been proposed along the years, and of them the permeation against vacuum (PAV) has been selected as the most suitable for DEMO. To perform this kind of experiments at laboratory scale, hydrogen isotopes cannot be generated in the liquid metal through nuclear reactions. Therefore, gas injection systems and concentration sensors are needed, and the support of modeling and chemical characterization activities is a key aspect.

- ''Detection of light ions in liquid metals''. There is a need to monitor the content of H, and more specifically the content of tritium, during the operation of the experiment. The reference solution for monitoring is the chemical analysis off-beam by means of PbLi specimens extracted from the loop. An on-line monitoring is foreseen by the development of two sensors for hydrogen isotopes; the first one is based on the permeation against vacuum technology; the second one, based on electrochemical measurements.

- ''Modelling activities in support of the experiments''. The modelling is an essential tool for the definition of the experiments. It compiles all physic-chemical processes with the operational parameters of the CLIPPER loop to obtain results in the limit of detection of the equipment and comparable to what is expected. One of the most attractive principles of nuclear fusion is that the radioactive waste produced in a commercial reactor should be classified as Low-Level Waste (LLW) within 100 years after the end of life (EOL).

-'' Analysis activities in support of the experiments''. A proper characterization of the PbLi materials is fundamental not only for the development of tritium efficient extraction methods, but also for tritium inventory control.

As a summary, the activities proposed in the framework of the Fusion LUTHYER project include a set of experimental and modeling tasks focused on some challenges in the liquid metals technology (PbLi) for its application to critical systems in the path to a DEMO reactor, as the tritium extraction system.

== Main results ==
To be completed at the end of the project (taken from the final report)

== Dissemination of project results (peer-reviewed publications and conference presentations) ==



== References ==
# B. Garcinuño et al., “The CIEMAT LiPb Loop Permeation Experiment”, Fusion Eng. Des. 146 (2019) 1228-1232
# B. Garcinuño et al., “The Tritium Extraction and Removal System for the DCLL-DEMO fusion reactor”, Nucl. Fusion 58 (2018) 095002
# B. Garcinuño et al., “Design and fabrication of a Permeator Against Vacuum prototype for small scale testing at Lead-Lithium facility”, Fusion Eng. Des. 124 (2017) 871-875
# F.R. Urgorri et al., "Theoretical evaluation of the tritium extraction from liquid metal flows through a free surface and through a permeable membrane" Nuclear Fusion 63 (2023) 63 046025
# F.R. Urgorri et al., A “Tritium transport modeling at system level for the EUROfusion dual coolant lithium-lead breeding blanket”,Nucl. Fusion, 57 (2017) 116045
# B. Garcinuño et al., “Development of an on-line sensor for hydrogen isotopes monitoring in flowing lithium at DONES” Fusion Eng. Des. 161 (2020) 112010
# B. Garcinuño et al., “Establishing technical specifications for PbLi eutectic alloy analysis and its relevance in fusion applications”, Nucl. Mater. Energy 30, pp. 101146 (2022)
# M. Malo et al., "Experimental refutation of the deuterium permeability in vanadium, niobium and tantalum" Fusion Engineering and Design 146-A (2019) 224-227
# I. Peñalva et al., "Hydrogen Transport Model in Eutectic PbLi for Data Evaluation in an Absorption-Desorption Experimental Facility" Fusion Science and Technology (2024) 80(3–4) 596–606
# M. Malo et al., "Experimental Determination of Hydrogen Isotope Transport Parameters in Vanadium" Membranes 2022, 12(6), 579
# D. Rapisarda et al., “The European Dual Coolant Lithium Lead breeding blanket for DEMO: status and perspectives”, Nucl. Fusion 61 (2021) 1150011
# I. Palermo et al., “Tritium production assessment for the DCLL EUROfusion DEMO”, Nucl. Fusion 56 (2016) 104001
# I. Palermo et al., “Radiological impact mitigation of waste coming from the European fusion reactor DEMO with DCLL breeding blanket” Fusion Eng. Des. 124 (2017) 1257-1262
# G. A. Spagnuolo et al., "Integration issues on tritium management of the European DEMO Breeding Blanket and ancillary systems" Fusion Engineering and Design 171 (2021) 112573
# M. Utili et al., "Design and Integration of the WCLL Tritium Extraction and Removal System into the European DEMO Tokamak Reactor" Energies 2023, 16(13), 5231

[[File:File.png]]


<hr>
[[LNF:Nationally Funded Projects|Back to list of nationally funded projects]]

[[Category:LNF Nationally Funded Projects]]

LNF: FIRESTELL. Física de los reactores de fusión de tipo stellarator: optimización del campo magnético, predicción de escenarios de plasma e identificación de puntos de diseño (2025-2028)

2025-12-10T09:56:30Z

Elena.delaluna: /* Dissemination of project results (peer-reviewed publications and conference presentations) */

== LNF - Nationally funded project ==

'''Title''': '''Física de los reactores de fusión de tipo stellarator: optimización del campo magnético, predicción de escenarios de plasma e identificación de puntos de diseño '''

'''Reference''': PID2024-155558OB-I00

'''Programme and date''': Plan Estatal de Investigación Científica, Técnica y de Innovación 2024-2027

'''Programme type (Modalidad de proyecto)''': Proyectos de Generación de Conocimiento 2024

'''Area/subarea (Área temática / subárea)''': Ciencias Físicas / Física de partículas y nuclear.

'''Principal Investigator(s)''': [https://orcid.org/0000-0001-8510-1422 José Luis Velasco] e [https://orcid.org/0000-0003-3118-3463 Iván Calvo]

'''Project type''': Proyecto individual / coordinado

'''Start-end dates''': 01/09/2025 - 30/08/2028

'''Financing granted (direct costs)''': 105.000 €

== Description of the project ==

El stellarator presenta una serie de ventajas respecto al tokamak, el otro concepto destacado para ser la base de los reactores de fusión por confinamiento magnético. En ambos casos se utiliza un campo magnético con superficies toroidales anidadas para confinar un plasma formado por electrones y núcleos de isótopos de hidrógeno. Los tokamaks tienen simetría axial y, por tanto, son más sencillos de diseñar y construir, pero la operación de reactores de tipo tokamaks es problemática: dado que la generación de parte del campo magnético confinante del tokamak depende de una corriente inducida en el plasma, la operación continua es más difícil y estos dispositivos son vulnerables frente a inestabilidades de corriente. Los stellarators evitan la necesidad de esta corriente por medio de un campo magnético tridimensional, que es generado por bobinas externas y que ha de ser cuidadosamente diseñado (optimizado, en la terminología habitual) para garantizar un buen confinamiento. En consecuencia, los stellarators son más difíciles de diseñar y construir, pero ofrecen un concepto intrínsecamente estable y de operación continua para plantas de fusión comerciales.

El escalado desde los stellarators actuales a los reactores implica un aumento de tamaño y coste significativo, así como regímenes de plasma inexplorados. Para minimizar los riesgos científicos y económicos, el diseño de los reactores de tipo stellarator ha de apoyarse fuertemente en la teoría y simulaciones numéricas avanzadas capaces de hacer predicciones precisas. El objetivo global de este proyecto es desarrollar y validar herramientas numéricas para resolver desafíos cruciales en el camino hacia los reactores de tipo stellarator, y por lo tanto ayudar a acelerar la llegada de la energía de fusión. El proyecto se organiza en torno a tres tareas generales: (1) optimizar campos magnéticos que puedan ser la base de reactores de tipo stellarator, (2) predecir el comportamiento del plasma confinado por estos campos magnéticos y (3) identificar puntos de diseño (por ejemplo, tamaño e intensidad del campo magnético) físicamente viables para los reactores. Los objetivos generales dentro de cada tarea se resumen a continuación.

(1) Evaluar (y, en su caso, mejorar) el desempeño, desde el punto de vista de la física, de las configuraciones de la familia CIEMAT-QI como candidatas para reactores de tipo stellarator y explorar el potencial de la nueva noción de omnigeneidad a trozos.

(2) Validar ideas teóricas y códigos numéricos (y aplicarlas a problemas no resueltos) sobre dos aspectos críticos de la física de plasmas en reactores stellarator: turbulencia y confinamiento de iones energéticos, y sobre la interacción entre los dos.

(3) Usar modelos simplificados basados en leyes de escala teóricas y empíricas, y ligaduras generales de tecnología de reactores para identificar parámetros de reactores potencialmente viables y para caracterizar sus regímenes de plasma. Aplicar los códigos precisos de la tarea (2) a estos parámetros.

Este proyecto está bien alineado con la hoja de ruta 'European Research Roadmap to the Realisation of Fusion Energy' elaborada por la UE, que está dividida en ocho misiones, y una de las cuales tiene como objetivo llevar el concepto del stellarator a la madurez. Una de las metas en el medio y largo plazo es desarrollar las capacidades requeridas para tomar una decisión sobre la siguiente generación de stellarators en el camino hacia la fusión comercial.


== Main results ==
To be completed at the end of the project (final report)

== Dissemination of project results (peer-reviewed publications and conference presentations) ==
Enter text here

== References ==



<hr>
[[LNF:Nationally Funded Projects|Back to list of nationally funded projects]]

[[Category:LNF Nationally Funded Projects]]

LNF: ENTORNO DISTRIBUIDO DE TIEMPO REAL PARA GESTION DE ALARMAS DE DISRUPCION CON MULTIPLES PREDICTORES EN PULSO LARGO: REENTRENAMIENTO ON-LINE Y CAMBIO EN CALIENTE DE PREDICTOR

2025-12-10T09:55:07Z

Elena.delaluna: /* Description of the project */

== LNF - Nationally funded project ==

'''Title''': '''ENTORNO DISTRIBUIDO DE TIEMPO REAL PARA GESTION DE ALARMAS DE DISRUPCION CON MULTIPLES PREDICTORES EN PULSO LARGO: REENTRENAMIENTO ON-LINE Y CAMBIO EN CALIENTE DE PREDICTOR'''

'''Reference''': PID2022-137680OB-C31

'''Programme and date''': Proyectos de ... Año

'''Programme type (Modalidad de proyecto)''':

'''Area/subarea (Área temática / subárea)''': Energía

'''Principal Investigator(s)''': [https://orcid.org/0000-0002-1622-3984 Jesús Vega] [https://orcid.org/0000-0003-4199-9335 Rodrigo Castro]

'''Project type''': Coordinado (CIEMAT , Departamento de Informática y Automática - UNED , Departamento de Ingeniería Telemática y Electrónica - UPM)

'''Start-end dates''': dd/mm/yyyy - dd/mm/yyyy

'''Financing granted (direct costs)''': 0 €

== Description of the project ==

Enter text here



== Main results ==
To be completed at the end of the project (final report)

== Dissemination of project results (peer-reviewed publications and conference presentations) ==

== References ==
<references />


<hr>
[[LNF:Nationally Funded Projects|Back to list of nationally funded projects]]

[[Category:LNF Nationally Funded Projects]]

LNF: Exploration of novel (anti) corrosion and permeation barriers (EXCORPION)

2025-12-10T09:54:31Z

Elena.delaluna: /* Description of the project */

== LNF - Nationally funded project ==
'''Title''': Exploration of novel (anti) corrosion and permeation
barriers (EXCORPION)

'''Reference''': PID2022-141926OA-I00

'''Programme and date''': Proyectos de Generación de Conocimiento, convocatoria 2022

'''Programme type (Modalidad de proyecto)''': Tipo A

'''Area/subarea (Área temática / subárea)''': Energía y transporte/Energía

'''Principal Investigator(s)''': Elisabetta Carella [https://orcid.org/0000-0002-4802-2546] [https://wiki.fusion.ciemat.es/wiki/User:Elisabetta] and Marta Malo [https://orcid.org/0000-0002-0093-5004]

'''Project type''': Proyecto individual

'''Start-end dates''': 01/09/2023 - 01/09/2026

'''Financing granted (direct costs)''': 90000 €

[[File:Logo EXCORPIONv2-transformed.png|200px|thumb|left|Caption]File:File.png|200px|thumb|right|Caption]]

== Description of the project ==

United Nations (UN) has declared a State of Climate Emergency until carbon neutrality
has been reached worldwide. EU has assumed a leading position in decarbonization,
going for a climate-neutral Europe in 2050. Much of this energy is still produced from
burning fossil fuels on a massive scale.

The international effort on
the development of
alternative energy systems,
see the
CIEMAT
involved with different innovative projects.
The development of new materials is a key question in different areas.
An urgent need for
developing advanced multi-functional coatings that can provide
protection against corrosion, gas permeation and/or provide determined features to
structural and functional base materials has been identified for multiple technological
applications.
For example,
a suitable protective layer for
structural steels
to minimize
tritium permeation and corrosive effects of the
PbLi
is fundamental for the development
of
some
key fusion reactor components.
High reflectivity and electrical conductivity
coatings are required for the new generati
on of solar cells. Low permeability is expected
for the development of hydrogen storage methods. Corrosion protection against molten
salts is required for applications
under nuclear fission conditions
, but also a protection of
the structural material from hydrogen embrittlement due to permeation.

The global objective of the project is to
promote the development of coating
technologies
for applications in the Energy
sector.
Complex multifunctional coatings are key pieces for the consecution of sustainable and
safe new energy sources and must fulfil slightly different requirements depending on the
specific working area.
Due to the extreme expected operational
conditions, the most
restrictive demands are imposed for use in Fusion devices. In particular, suitable
chemical composition in order to reduce neutron activation and hence minimize
radioactive waste is critical for the design of future fusion plants. This
consideration will
serve as a starting point for the selection of the candidate compositions for the
design
and fabrication
stage, together with the current existing background.
Cascade
validation of the fabricated coatings
is proposed from a lesser to
a
greater level of
specificity. This way, even though not every single requirement is met for (all)
of
the
examined coatings, their potential use in different disciplines will be considered
depending on the satisfied properties.
EXCORPION will study the above new materials
solutions in terms of
# compatibility with different corrosive materials
# hydrogen isotopes permeation reduction
# radiation tolerance by dedicated gamma and ion irradiation experiments
# validation to a system level and scale-up to welding and newgeometries.

The
proposal
of
this
transversal
project
between
various
research
groups
highlights
the
need
for
synergies
to
obtain
new
materials
capable
of
meeting
all
the
extreme
conditions
to
which
they
are
subjected
and
improving
the
efficiency
of
these
alternative
sources
for
energy
production,
with
the
ultimate
goal
of
being
a
real
alternative
to
fossil
fuels.



== Main results ==
To be completed at the end of the project (final report)

== Dissemination of project results (peer-reviewed publications and conference presentations) ==

== References ==
# M. Malo, A. Moroño and E. R. Hodgson, In situ luminescence qualifications of radiation damage in aluminas: F aggregation and Al colloids, Fusion Engineering and Design 89 (2014) 2179-2183.
# M. Malo, A. Moroño, and E.R. Hodgson, “Radioluminescence characterization of SiC and SiC/SiC”, Journal of Nuclear Materials 442 (2013) s404-s409.
# M. Carmona Gázquez, S. Bassini, T. Hernández and M. Utili “Al2O3 Coating as Barrier against corrosion in Pb-17Li” Fusion Engineering and Design Vol. 124, (2017) 837-840.
# P. Muñoz, et. al, “Radiation effects on deuterium permeation for PLD alumina coated Eurofer steel measured during 1.8 MeV electron irradiation” Journal of Nuclear Materials 512 (2018) 118 – 125
# T.Hernández, et al., “Corrosion protective action of different coatings for the helium cooled pebble breeder concept” Journal of Nuclear Materials 516 (2019) 160-168.
# T. Hernández, et al., “Corrosion behavior of diverse sputtered coatings for the helium cooled pebbles bed (HCPB) breeder concept” Nuclear Materials and Energy, 25 (2020) 100795.
# A. Moroño, E.R. Hodgson and M. Malo, “Radiation enhanced deuterium absorption for Al2O3 and macor ceramic”, Fusion Engineering and Design 88 (2013) 2488-2491.
# T. Hernández, et al., “Study of deuterium permeation, retention, and desorption in SiC coatings submitted to relevant conditions for breeder blanket applications: thermal cycling effect under electron irradiation and oxygen exposure” Journal of Nuclear Materials 557 (2021) 153219
# Gonzalez-Arrabal, R., Rivera, A., & Perlado, J. M. (2020). “Limitations for tungsten as plasma facing material in the diverse scenarios of the European inertial confinement fusion facility HiPER: Current status and new approaches” Matter and Radiation at Extremes, 5(5), 055201.
# Panizo-Laiz, et al., (2019). “Experimental and computational studies of the influence of grain boundaries and temperature on the radiation-induced damage and hydrogen behavior in tungsten” Nuclear Fusion, 59(8).
# C. Abed, et al., “Processing and Study of Optical and Electrical Properties of (Mg, Al) Co-Doped ZnO Thin Films Prepared by RF Magnetron Sputtering for Photovoltaic Application” Materials 13 (2020) 2146-2158.
# S. Fernández, et al.”Non-treated low temperature indium tin oxide fabricated in oxygen-free environment to low-cost silicon-based solar technology” Vacuum 184 (2021) 109783.
# S. Fernández, et al.,”Sputtered non-hydrogenated amorphous silicon as alternative absorber for silicon photovoltaic technology” Materials (2021), 14, 6550.
# S. Fernández, et al., “Roles of low temperature sputtered indium tin oxide for solar photovoltaic technology” Materials (2021), 14, Issue 24, 7758.
# S. Suárez, et al., Parameters to be considered for the development highly photoactive TiO2 layers on aluminium substrates by magnetron sputtering. Catalysis Today (In press).
# E. Carella, D. Rapisarda, S.Lenk. “Design of the CIEMAT Corrosion Loop for Liquid Metal Experiments” Applied Sciences, 12 (2022), 3104.
# E. Carella, C. Moreno, F. R. Urgorri, D. Rapisarda, A. Ibarra “Tritium modeling in HCPB breeder blanket at a system level” Fusion Engineering and Design, 124 (2017) 687-691.
# E. Carella, M. Gonzalez, R. Gonzalez-Arrabal “D-depth profiling in as-implanted and annealed Li-based Breeder Blanket ceramics” Journal of Nuclear Materials, Vol. 438, Issues 1–3 (2013) 193-198.

[[File:File.png]]


<hr>
[[LNF:Nationally Funded Projects|Back to list of nationally funded projects]]

[[Category:LNF Nationally Funded Projects]]

LNF: Exploration of novel (anti) corrosion and permeation barriers (EXCORPION)

2025-12-10T09:54:18Z

Elena.delaluna: /* Description of the project */

LNF: AID-DAEDALUS. : AI Driven Digital twin prototype of the TJ-II and OLMAT for Advanced Experimental Design, Analysis and Leading-edge Understanding of Stellarators physics (2025-2028)

2025-12-10T09:53:16Z

Elena.delaluna: /* Description of the project */

== LNF - Nationally funded project ==

'''Title''': '''AID-DAEDALUS. AI Driven Digital twin prototype of the TJ-II and OLMAT for Advanced Experimental Design, Analysis and Leading-edge Understanding of Stellarators physics'''

'''Reference''': PID2024-157659OB-I00

'''Programme and date''': Plan Estatal de Investigación Científica, Técnica y de Innovación 2024-2027

'''Programme type (Modalidad de proyecto)''': Proyectos de Generación de Conocimiento 2024

'''Area/subarea (Área temática / subárea)''': Energía y transporte / Energía

'''Principal Investigator(s)''': [https://orcid.org/0000-0002-5676-9631 Giuseppe Rattá Gutiérrez]

'''Project type''': Proyecto individual

'''Start-end dates''': 01/09/2025 - 30/08/2028

'''Financing granted (direct costs)''': 65000 €

== Description of the project ==

El proyecto AID-DAEDALUS busca crear prototipos de gemelos digitales impulsados por inteligencia artificial de los dispositivos de fusión TJ-II y OLMAT del CIEMAT. Su finalidad es simular, predecir y controlar en tiempo real el comportamiento del plasma y de los materiales sometidos a condiciones extremas, con el fin de optimizar los recursos y reducir los costes de las campañas experimentales. Para ello se aprovechará una amplia base de datos con más de cincuenta mil experimentos del TJ-II y los registros de OLMAT, que servirán para entrenar modelos de redes neuronales capaces de reproducir parámetros como la densidad electrónica, la radiación o los daños en tungsteno, y de generar señales sintéticas cuando las mediciones reales sean incompletas o defectuosas.

Durante tres años se desarrollarán bases de datos estandarizadas, modelos de inteligencia artificial y pruebas de control en tiempo real utilizando el supercomputador Turgalium. El proyecto cuenta con la colaboración de centros nacionales e internacionales y con la participación de varios doctorandos, y se espera que refuerce el liderazgo científico de España en el uso de inteligencia artificial aplicada a la energía de fusión, reduciendo los costes experimentales y promoviendo la transferencia de estas tecnologías a otros dispositivos europeos y a sectores como la ciencia de materiales o los sistemas energéticos avanzados.


== Main results ==
To be completed at the end of the project (final report)

== Dissemination of project results (peer-reviewed publications and conference presentations) ==

== References ==
<references />


<hr>
[[LNF:Nationally Funded Projects|Back to list of nationally funded projects]]

[[Category:LNF Nationally Funded Projects]]

LNF:Estudios del confinamiento mejorado y de impurezas en los Stellarators TJ-II y W7-X mediante inyección de pastillas criogénicas (Pellets) y encapsulados de impurezas (TESPEL)

2025-12-10T09:52:02Z

Elena.delaluna: /* Dissemination of project results (peer-reviewed publications and conference presentations) */

== LNF - Nationally funded project ==

'''Title''': '''Estudios del confinamiento mejorado y de impurezas en los Stellarators TJ-II y W7-X mediante inyección de pastillas criogenicas (Pellets) y encapsulados de impurezas (TESPEL)'''

'''Reference''': PID2023-148697OB-I00

'''Programme and date''': Proyectos de Generación de Conocimiento 2023

'''Programme type (Modalidad de proyecto)''': Proyectos investigación orientada

'''Area/subarea (Área temática / subárea)''': Energy & Transport / Energy

'''Principal Investigator(s)''': [https://orcid.org/0000-0002-5223-391X Isabel García-Cortés ][https://orcid.org/0000-0002-5881-1442 Kieran Joseph McCarthy]

'''Project type''': Proyecto individual

'''Start-end dates''': 01/09/2024 - 31/08/2027

'''Financing granted (direct costs)''': 130.000 €

== Description of the project ==

The aim of this project, which falls within the realm of magnetic confinement fusion, is to continue and broaden the research initiated in projects ENE2013-48679-R, FIS2017-89326-R and PID2020-116599RB-I00 on fuelling and impurity control in plasmas created in the stellarators TJ-II (Ciemat, Madrid), W7-X (Greifswald, Germany) and LHD (Toki, Japan). This research aims to investigate issues related to these two issue which are critical for achieving steady-state operation of helical-type fusion reactors. In particular, it is necessary to identify operational scenarios that ensure adequate plasma fuelling and short impurity confinement times, in particular, for heavy ions. It is intended that this work will support the European stellarator programme and contribute to the development and scientific exploitation of stellarators, a priority highlighted in the document "Fusion Electricity: a roadmap to the realization of fusion energy" (EFDA 2012).

1. The first aim is to investigate aspects of pellet injection that are still not fully understood as well as to understand better how pellets affect plasma magnetic activity, plasma turbulence and plasma performance. For this, the medium-sized heliac TJ-II will be used. It is equipped with a cryogenic pellet injector (PI) for producing solid hydrogen pellets that can be injected at high velocity into the plasma. During previous projects it was found that pellet injection into TJ-II results in enhanced plasma performance (simultaneously higher electron density and ion temperature, larger stored diamagnetic energy, longer particle confinement, higher plasma beta) <ref>1</ref> <ref>2</ref>. It was also seen how the injection of additional fuel pellets further increases and maintains this enhanced plasma performance. It is now necessary to understand the underlying physics of these experimental observations. This will be done using available codes to evaluate neoclassical and turbulent contributions.

2. The second aim is to continue to support and expand impurity transport studies in TJ-II, W7-X and LHD. Under the umbrella of a trilateral collaboration (2020-2029) with the National Institute for Fusion Science (Japan) and IPP-Max-Planck (Greifswald, Germany), the Tracer-Encapsulated Solid Pellet (TESPEL) method is now employed on TJ-II, W7-X and LHD. TESPELs are polystyrene spheres (diameter <1 mm) loaded with small quantities of selected impurities (atomic elements other than fuel). Thus, TESPEL allows delivering a precise quantify of tracer to a preselected location in the plasma core, after which its transport can be evaluated. An important aspect of previous projects was the establishment of a laboratory to fabricate TESPELs at Ciemat. Since then several hundred TESPELs prepared at Ciemat have been injected successfully into plasmas created in these devices. Thus, key goals of this current project are to continue TESPEL fabrication at this laboratory, thereby allowing Ciemat to maintain its fruitful collaborations with W7-X and LHD, and to expand TESPEL based impurity control studies. For instance, during recent experiments with TESPEL at LHD, project members determined that mid-/high- Z atomic ions can be flushed out of a high-density plasma if Li-granules are dropped continuously into the plasma edge <ref>3</ref>. When results were compared with results from reference plasmas, confinement times of high-Z ions were reduced by a factor 4 or more. It is extend to explore further this new operational scenario for stellarators.

== Main results ==
To be completed at the end of the project (final report)

== Dissemination of project results (peer-reviewed publications and conference presentations) ==

PEER-REVIEWED ARTICLES ASSOCIATED TO THIS PROJECT (SINCE 2024)

[1] Enhanced confinement induced by pellet injection in the stellarator TJ-II, I. García-Cortes, K. J. McCarthy, T. Estrada, V. Tribaldos, B. van Milligen, E. Ascasíbar, R. Carrasco, A. A. Chmyga, R. García, J. Hernández-Sánchez, C. Hidalgo, S. Kozachek, F. Medina, D. Medina-Roque, M. A. Ochando, J. L. de Pablos, N. Panadero, I. Pastor and TJ-II Team, Phys. Plasmas 30 (2023) 072506. https://doi.org/10.1063/5.0151395

[2] Multi-pellet injection into the NBI-heated phase of TJ-II plasmas, K. J. McCarthy, I. García-Cortés, A. Alonso, A. Arias-Camisón, E. Ascasíbar, A. Baciero, A. Cappa, R. Carrasco, O. O. Chmyga, T. Estrada, R. García, J. Hernández-Sánchez, F. J. Herranz, O. S. Kozachok, B. López Miranda, F. Medina, D. Medina-Roque, B. van Milligen, M. Navarro, M. A. Ochando, J. L. de Pablos, N. Panadero, I. Pastor, J. de la Riva, M. C. Rodríguez, D. Tafalla, V. Tribaldos and TJ-II Team, Nucl. Fusion 64 (2024) 066019, https://doi.org/10.1088/1741-4326/ad4047.

[3] Reduction of impurity confinement times in lithium-powder induced reduced-turbulence plasmas in the LHD, D. Medina-Roque, F. Nespoli, I. García-Cortés, K. J. McCarthy, N. Tamura, C. Suzuki, M. Goto, T. Kawate, Y. Kawamoto, M. Yoshinuma, K. Ida, K. Tanaka, T. Tokuzawa, H. Funaba, I. Yamada and the LHD team, in preparation for Nucl. Fusion Lett.

POSTERS AND TALKS IN CONFERENCES SINCE 2024

[1] Characterization of enhanced plasma performance phase after pellet injections in the TJ-II stellarator, I. García-Cortés, K. J. McCarthy, B. Van Milligen, T. Estrada, D. Medina-Roque, A. Baciero, B. A. Carreras, A. Cappa, A. A. Chmyga, F. Medina, L. Garcia, R. García, J. Hernández-Sánchez, F. J. Hernanz, A. S. Kozachek, F. Lapayese, B. Lopez-Miranda, D. Lopez-Bruna, V. Tribaldos, J. L. De Pablos, N. Panadero, I. Pastor, A. de La Peña, P. Pons-Villalonga, M.C. Rodriguez, D. Tafalla and TJ-II team, 30th IAEA Fusion Energy Conference, Chengdu, China (2025).

[2] Interpreting structures observed in pellet ablation profiles in the stellarator TJ-IIInterpreting structures observed in pellet ablation profiles in the stellarator TJ-II, K. J. McCarthy, I. García-Cortés, B. van Milligen, A. Baciero, R. Carrasco, T. Estrada, R. García, J. Hernández-Sánchez, B. López-Miranda, F. Medina, D. Medina-Roque, M. Navarro, N. Panadero, I. Pastor, M. C. Rodríguez and TJ-II Team, 30th IAEA Fusion Energy Conference, Chengdu, China (octubre 2025).

[3] Impact of Li-granule injection on the improvement of energy transport and the expulsion of impurities in the LHD heliotron, D. Medina-Roque, K. J. McCarthy, N. Tamura, I. García-Cortés, K. Tanaka, F. Nespoli, M. Shoji, S. Masuzaki, H. Funaba, C. Suzuki, A. Mollen, R. Lunsford, K. Ida, M. Yoshinuma, M. Goto, Y. Kawamoto, T. Kawate, T. Tokuzawa, I. Yamada and the LHD Experimental Team, 30th IAEA Fusion Energy Conference, Chengdu, China (2025).

[4] Confinement modelling pf enhanced plasma performance after multiple pellet injections into the TJ-II stellarator, V. Tribaldos, I. García-Cortés, K. J. McCarthy, D. Medina-Roque, A. Baciero, T. Estrada, D. López-Bruna, F. Medina, B. van Milligen, J. L. de Pablos, N. Panadero, I. Pastor, J. de la Riva and TJ-II Team, J. M. Reynolds-Barredo, O. O. Chmyga, O. S. Kozachok, 30th IAEA Fusion Energy Conference, Chengdu, China (2025).

[5] Transport in high-performance plasmas in the TJ-II stellarator: from first-principles simulations to experimental validation, J. M. García-Regaña, …, J. M. Fontdecaba, …, I. García-Cortés, …, J. Hernández-Sánchez, …, B. López-Miranda, …, K. J. McCarthy, …, D. Medina-Roque, P. Méndez, … N. Panadero, …, N. Tamura et al., 30th IAEA Fusion Energy Conference, Chengdu, China (2025).

[6] Tungsten erosion and injection investigations in the stellarator Wendelstein 7-X during OP2.2, D. Chandra-Prakash, N. Tamura, … D. Medina-Roque, … I. García-Cortés, … K. J. McCarthy, et al., 20th International Conference on Plasma-Facing Materials and Components for Fusion Applocations, Ljubljana, Slovenia (2025).

[7] Characterisation of the pellet cloud drift in stellarators, G. Kocsis, J. Baldzuhn, R. Bussiahn, A. Buzás, G. Cseh, I. García-Cortés, K. J. McCarthy, D. Medina-Roque, N. Panadero, T. Szepesi, N. Tamura, M.B. Vavrik, Th. Wegner, TJ-II Team and W7-X Team, 51st EPS Conference on Plasma Physics, Vilnius, Lituania (2025).

[8] Study of the density limit physics for stellarator devices by means of an energy balance model, J. Gallego, A. Alonso, A. Bustos, T. Estrada, B. López-Miranda, A. Baciero, A. Cappa, K. J. McCarthy, I. García-Cortés, J. de la Riva Villén, F. Medina, N. Panadero and the TJ-II Team, 51st EPS Conference on Plasma Physics, Vilnius, Lituania (2025).

[9] Magnetic configuration effects on pellet fuelling in stellarators, N. Panadero, K.J. McCarthy, J. Baldzuhn, J. Hernández-Fernández, F. Köchl, G. Kocsis, A. I. Mohammed, N. Tamura, M.B. Vavrik, E. Villalobos Granados, T. Szepesi, and TJ-II and W7-X teams, 51st EPS Conference on Plasma Physics, Vilnius, Lituania (2025).


<hr>
[[LNF:Nationally Funded Projects|Back to list of nationally funded projects]]

[[Category:LNF Nationally Funded Projects]]

LNF: FIRESTELL. Física de los reactores de fusión de tipo stellarator: optimización del campo magnético, predicción de escenarios de plasma e identificación de puntos de diseño (2025-2028)

2025-12-10T09:50:03Z

Elena.delaluna: /* Dissemination of project results (peer-reviewed publications and conference presentations) */

== LNF - Nationally funded project ==

'''Title''': '''Física de los reactores de fusión de tipo stellarator: optimización del campo magnético, predicción de escenarios de plasma e identificación de puntos de diseño '''

'''Reference''': PID2024-155558OB-I00

'''Programme and date''': Plan Estatal de Investigación Científica, Técnica y de Innovación 2024-2027

'''Programme type (Modalidad de proyecto)''': Proyectos de Generación de Conocimiento 2024

'''Area/subarea (Área temática / subárea)''': Ciencias Físicas / Física de partículas y nuclear.

'''Principal Investigator(s)''': [https://orcid.org/0000-0001-8510-1422 José Luis Velasco] e [https://orcid.org/0000-0003-3118-3463 Iván Calvo]

'''Project type''': Proyecto individual / coordinado

'''Start-end dates''': 01/09/2025 - 30/08/2028

'''Financing granted (direct costs)''': 105.000 €

== Description of the project ==

El stellarator presenta una serie de ventajas respecto al tokamak, el otro concepto destacado para ser la base de los reactores de fusión por confinamiento magnético. En ambos casos se utiliza un campo magnético con superficies toroidales anidadas para confinar un plasma formado por electrones y núcleos de isótopos de hidrógeno. Los tokamaks tienen simetría axial y, por tanto, son más sencillos de diseñar y construir, pero la operación de reactores de tipo tokamaks es problemática: dado que la generación de parte del campo magnético confinante del tokamak depende de una corriente inducida en el plasma, la operación continua es más difícil y estos dispositivos son vulnerables frente a inestabilidades de corriente. Los stellarators evitan la necesidad de esta corriente por medio de un campo magnético tridimensional, que es generado por bobinas externas y que ha de ser cuidadosamente diseñado (optimizado, en la terminología habitual) para garantizar un buen confinamiento. En consecuencia, los stellarators son más difíciles de diseñar y construir, pero ofrecen un concepto intrínsecamente estable y de operación continua para plantas de fusión comerciales.

El escalado desde los stellarators actuales a los reactores implica un aumento de tamaño y coste significativo, así como regímenes de plasma inexplorados. Para minimizar los riesgos científicos y económicos, el diseño de los reactores de tipo stellarator ha de apoyarse fuertemente en la teoría y simulaciones numéricas avanzadas capaces de hacer predicciones precisas. El objetivo global de este proyecto es desarrollar y validar herramientas numéricas para resolver desafíos cruciales en el camino hacia los reactores de tipo stellarator, y por lo tanto ayudar a acelerar la llegada de la energía de fusión. El proyecto se organiza en torno a tres tareas generales: (1) optimizar campos magnéticos que puedan ser la base de reactores de tipo stellarator, (2) predecir el comportamiento del plasma confinado por estos campos magnéticos y (3) identificar puntos de diseño (por ejemplo, tamaño e intensidad del campo magnético) físicamente viables para los reactores. Los objetivos generales dentro de cada tarea se resumen a continuación.

(1) Evaluar (y, en su caso, mejorar) el desempeño, desde el punto de vista de la física, de las configuraciones de la familia CIEMAT-QI como candidatas para reactores de tipo stellarator y explorar el potencial de la nueva noción de omnigeneidad a trozos.

(2) Validar ideas teóricas y códigos numéricos (y aplicarlas a problemas no resueltos) sobre dos aspectos críticos de la física de plasmas en reactores stellarator: turbulencia y confinamiento de iones energéticos, y sobre la interacción entre los dos.

(3) Usar modelos simplificados basados en leyes de escala teóricas y empíricas, y ligaduras generales de tecnología de reactores para identificar parámetros de reactores potencialmente viables y para caracterizar sus regímenes de plasma. Aplicar los códigos precisos de la tarea (2) a estos parámetros.

Este proyecto está bien alineado con la hoja de ruta 'European Research Roadmap to the Realisation of Fusion Energy' elaborada por la UE, que está dividida en ocho misiones, y una de las cuales tiene como objetivo llevar el concepto del stellarator a la madurez. Una de las metas en el medio y largo plazo es desarrollar las capacidades requeridas para tomar una decisión sobre la siguiente generación de stellarators en el camino hacia la fusión comercial.


== Main results ==
To be completed at the end of the project (final report)

== Dissemination of project results (peer-reviewed publications and conference presentations) ==
<references />


<hr>
[[LNF:Nationally Funded Projects|Back to list of nationally funded projects]]

[[Category:LNF Nationally Funded Projects]]