Sehila M. Gonzalez de Vicente
Current Organizations / Institutes
The organizations/institutes from the scholar's latest article
Sehila M. Gonzalez de Vicente has a total of 43 co-authors. Here are the top co-authors by number of shared publications:
- Andreas Dinklage
Max Planck Institute for Plasma Physics, Greifswald, Germany
3 shared publications E.R. Hodgson
3 shared publications- Alejandro Moroño
Euratom/CIEMAT Fusion Association, Madrid, Spain
2 shared publications - Andrea Murari
Consorzio RFX (CNR, ENEA, INFN, Università di Padova, Acciaierie Venete SpA), Corso Stati Uniti 4, 35127 Padova, Italy
2 shared publications - Geert Verdoolaege
Ghent University
2 shared publications - Jesus Vega
Laboratorio Nacional de Fusión, CIEMAT, Madrid, Spain
2 shared publications
Latest Publications
- Open Access
- 20 March 2023
- Published by IOP Publishing in Nuclear Fusion
- Vol. 63 (5) , 057001
The IAEA DEMO Programme Workshop Series: 2012–2021 report
The IAEA DEMO Programme Workshop Series was initiated to be the reference forum to debate, evaluate and establish the next steps to be taken within the international fusion community to deliver fusion as a reliable source of clean energy. The DEMO programme refers predominantly to a future magnetic confinement Tokamak design concept, after the ITER project, with a goal of delivering electricity to the grid. To enable this, the programme workshop series provides a unique frame where the discussion and analysis of the progress and findings of the various DEMO programmes, and not just the presentation of results being the major goals. More recently, due to the construction development of ITER, the workshop has also provided a forum to bring together the fusion community and industry. This is an important development for DEMO programmes, which will be more reliant on industry given their focus on devices proximate to a commercial fusion power plant. In this paper a summary of all editions of this workshop (2012–2013–2015–2016–2018–2019) up to 2021 are summarized. Topics addressed are listed and findings and open questions pointed out for each edition.
- 20 March 2023
- Published by IOP Publishing in Nuclear Fusion
- Vol. 63 (5) , 057001
Open AccessThe IAEA DEMO Programme Workshop Series: 2012–2021 report
The IAEA DEMO Programme Workshop Series was initiated to be the reference forum to debate, evaluate and establish the next steps to be taken within the international fusion community to deliver fusion as a reliable source of clean energy. The DEMO programme refers predominantly to a future magnetic confinement Tokamak design concept, after the ITER project, with a goal of delivering electricity to the grid. To enable this, the programme workshop series provides a unique frame where the discussion and analysis of the progress and findings of the various DEMO programmes, and not just the presentation of results being the major goals. More recently, due to the construction development of ITER, the workshop has also provided a forum to bring together the fusion community and industry. This is an important development for DEMO programmes, which will be more reliant on industry given their focus on devices proximate to a commercial fusion power plant. In this paper a summary of all editions of this workshop (2012–2013–2015–2016–2018–2019) up to 2021 are summarized. Topics addressed are listed and findings and open questions pointed out for each edition.
- Open Access
- 15 March 2023
- Published by IOP Publishing in Nuclear Fusion
- Vol. 63 (4) , 047001
Summary report of the 4th IAEA Technical Meeting on Fusion Data Processing, Validation and Analysis (FDPVA)
The objective of the Fourth Technical Meeting on Fusion Data Processing, Validation and Analysis was to provide a platform during which a set of topics relevant to fusion data processing, validation and analysis are discussed with the view of extrapolating needs to next step fusion devices such as ITER. The validation and analysis of experimental data obtained from diagnostics used to characterize fusion plasmas are crucial for a knowledge-based understanding of the physical processes governing the dynamics of these plasmas. This paper presents the recent progress and achievements in the domain of plasma diagnostics and synthetic diagnostics data analysis (including image processing, regression analysis, inverse problems, deep learning, machine learning, big data and physics-based models for control) reported at the meeting. The progress in these areas highlight trends observed in current major fusion confinement devices. A special focus is dedicated on data analysis requirements for ITER and DEMO with a particular attention paid to artificial intelligence for automatization and improving reliability of control processes.
- 15 March 2023
- Published by IOP Publishing in Nuclear Fusion
- Vol. 63 (4) , 047001
Open AccessSummary report of the 4th IAEA Technical Meeting on Fusion Data Processing, Validation and Analysis (FDPVA)
The objective of the Fourth Technical Meeting on Fusion Data Processing, Validation and Analysis was to provide a platform during which a set of topics relevant to fusion data processing, validation and analysis are discussed with the view of extrapolating needs to next step fusion devices such as ITER. The validation and analysis of experimental data obtained from diagnostics used to characterize fusion plasmas are crucial for a knowledge-based understanding of the physical processes governing the dynamics of these plasmas. This paper presents the recent progress and achievements in the domain of plasma diagnostics and synthetic diagnostics data analysis (including image processing, regression analysis, inverse problems, deep learning, machine learning, big data and physics-based models for control) reported at the meeting. The progress in these areas highlight trends observed in current major fusion confinement devices. A special focus is dedicated on data analysis requirements for ITER and DEMO with a particular attention paid to artificial intelligence for automatization and improving reliability of control processes.
- 6 January 2023
- Published by IOP Publishing in Plasma Physics and Controlled Fusion
- Vol. 65 (2) , 020201
Papers from the 4th IAEA technical meeting on fusion data processing validation and analysis (FDPVA)
- 6 January 2023
- Published by IOP Publishing in Plasma Physics and Controlled Fusion
- Vol. 65 (2) , 020201
Papers from the 4th IAEA technical meeting on fusion data processing validation and analysis (FDPVA)
- Open Access
- 30 May 2022
- Published by IOP Publishing in Nuclear Fusion
- Vol. 62 (8) , 085001
Overview on the management of radioactive waste from fusion facilities: ITER, demonstration machines and power plants
In the absence of official standards and guidelines for nuclear fusion plants, fusion designers adopted, as far as possible, well-established standards for fission-based nuclear power plants (NPPs). This often implies interpretation and/or extrapolation, due to differences in structures, systems and components, materials, safety mitigation systems, risks, etc. This approach could result in the consideration of overconservative measures that might lead to an increase in cost and complexity with limited or negligible improvements. One important topic is the generation of radioactive waste in fusion power plants. Fusion waste is significantly different to fission NPP waste, i.e. the quantity of fusion waste is much larger. However, it mostly comprises low-level waste (LLW) and intermediate level waste (ILW). Notably, the waste does not contain many long-lived isotopes, mainly tritium and other activation isotopes but no-transuranic elements. An important benefit of fusion employing reduced-activation materials is the lower decay heat removal and rapid radioactivity decay overall. The dominant fusion wastes are primarily composed of structural materials, such as different types of steel, including reduced activation ferritic martensitic steels, such as EUROFER97 and F82H, AISI 316L, bainitic, and JK2LB. The relevant long-lived radioisotopes come from alloying elements, such as niobium, molybdenum, nickel, carbon, nitrogen, copper and aluminum and also from uncontrolled impurities (of the same elements, but also, e.g. of potassium and cobalt). After irradiation, these isotopes might preclude disposal in LLW repositories. Fusion power should be able to avoid creating high-level waste, while the volume of fusion ILW and LLW will be significant, both in terms of pure volume and volume per unit of electricity produced. Thus, efforts to recycle and clear are essential to support fusion deployment, reclaim resources (through less ore mining) and minimize the radwaste burden for future generations.
- 30 May 2022
- Published by IOP Publishing in Nuclear Fusion
- Vol. 62 (8) , 085001
Open AccessOverview on the management of radioactive waste from fusion facilities: ITER, demonstration machines and power plants
In the absence of official standards and guidelines for nuclear fusion plants, fusion designers adopted, as far as possible, well-established standards for fission-based nuclear power plants (NPPs). This often implies interpretation and/or extrapolation, due to differences in structures, systems and components, materials, safety mitigation systems, risks, etc. This approach could result in the consideration of overconservative measures that might lead to an increase in cost and complexity with limited or negligible improvements. One important topic is the generation of radioactive waste in fusion power plants. Fusion waste is significantly different to fission NPP waste, i.e. the quantity of fusion waste is much larger. However, it mostly comprises low-level waste (LLW) and intermediate level waste (ILW). Notably, the waste does not contain many long-lived isotopes, mainly tritium and other activation isotopes but no-transuranic elements. An important benefit of fusion employing reduced-activation materials is the lower decay heat removal and rapid radioactivity decay overall. The dominant fusion wastes are primarily composed of structural materials, such as different types of steel, including reduced activation ferritic martensitic steels, such as EUROFER97 and F82H, AISI 316L, bainitic, and JK2LB. The relevant long-lived radioisotopes come from alloying elements, such as niobium, molybdenum, nickel, carbon, nitrogen, copper and aluminum and also from uncontrolled impurities (of the same elements, but also, e.g. of potassium and cobalt). After irradiation, these isotopes might preclude disposal in LLW repositories. Fusion power should be able to avoid creating high-level waste, while the volume of fusion ILW and LLW will be significant, both in terms of pure volume and volume per unit of electricity produced. Thus, efforts to recycle and clear are essential to support fusion deployment, reclaim resources (through less ore mining) and minimize the radwaste burden for future generations.
- 14 August 2020
- Published by IOP Publishing in Nuclear Fusion
- Vol. 60 (9) , 097002
Summary report of the 3rd IAEA technical meeting on fusion data processing validation and analysis (FDPVA)
- 14 August 2020
- Published by IOP Publishing in Nuclear Fusion
- Vol. 60 (9) , 097002
Summary report of the 3rd IAEA technical meeting on fusion data processing validation and analysis (FDPVA)
- 1 November 2018
- Published by Elsevier in Fusion Engineering and Design
- Vol. 136, 1237-1241
Safety classification of mechanical components for fusion application
- 1 November 2018
- Published by Elsevier in Fusion Engineering and Design
- Vol. 136, 1237-1241
Safety classification of mechanical components for fusion application
- 9 June 2017
- Published by IOP Publishing in Nuclear Fusion
- Vol. 57 (9) , 092011
Materials testing facilities and programmes for fission and ion implantation damage
- 9 June 2017
- Published by IOP Publishing in Nuclear Fusion
- Vol. 57 (9) , 092011
Materials testing facilities and programmes for fission and ion implantation damage
- 9 June 2017
- Published by IOP Publishing in Nuclear Fusion
- Vol. 57 (9) , 092009
Functional materials for tokamak in-vessel systems—status and developments
- 9 June 2017
- Published by IOP Publishing in Nuclear Fusion
- Vol. 57 (9) , 092009
Functional materials for tokamak in-vessel systems—status and developments
- 1 October 2011
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 417 (1-3) , 790-793
A model for electrical degradation of insulators due to ionic bombardment
- 1 October 2011
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 417 (1-3) , 790-793
A model for electrical degradation of insulators due to ionic bombardment
- 30 April 2009
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 386-388, 1002-1005
Electrical surface degradation of electron irradiated sapphire and silica
- 30 April 2009
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 386-388, 1002-1005
Electrical surface degradation of electron irradiated sapphire and silica