Conceptual design of a system of RMP coils for the TCABR tokamak

Detalhes bibliográficos
Autor(a) principal: Salvador, Felipe Machado
Data de Publicação: 2022
Tipo de documento: Dissertação
Idioma: eng
Título da fonte: Biblioteca Digital de Teses e Dissertações da USP
Texto Completo: https://www.teses.usp.br/teses/disponiveis/43/43134/tde-21112022-130617/
Resumo: The high confinement mode observed in tokamak plasmas is seen as the most promising operational regime for economically viable nuclear fusion power plants. A particular characteristic of the high confinement plasmas is the onset of periodic instabilities known as edge localized modes (ELMs). These instabilities generate unacceptably large heat fluxes on the divertor plates that erode the divertor and reduces significantly its life time on a future reactor. Therefore, there is a need to develop ELM control methods in large machines, such as ITER. Several experiments have demonstrated that the application of non-axisymetric resonant magnetic perturbations (RMPs), created by electric currents flowing in localised coils outside the plasma, can be used to control ELMs. Due to its efficiency, ELM control coils, also called RMP coils, were added to ITER baseline project. Although the RMP coils have been successfully used to suppress ELMs in various tokamaks, the numerical modelling of these plasma discharges reveal that current physical models are not capable of describing satisfactorily the observed effects. The lack of a trustworthy physical model to describe the impact of RMP fields in tokamak plasmas is a central topic when plasma physics scientists try to predict the plasma reaction to the RMP fields in ITER. In order to enhance the numerical results reliability, carefully designed experiments to validate physical models are being realised in several tokamaks around the globe. Here in Brazil, a significant upgrade of the TCABR tokamak, operated at Plasma Physics Laboratory of Institute of Physics of the University of São Paulo, is in progress. In this upgrade, it is planned the installation of six sets of RMP coils, which enable the TCABR to test physical models used to predict the plasma response to RMP fields. This work has the objective of designing the RMP coil sets that will be installed in TCABR, which enables the validation of physical models in a wide variety of plasma scenarios, RMP field configurations and magnetic spectra with a large range of poloidal and toroidal harmonics.
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spelling Conceptual design of a system of RMP coils for the TCABR tokamakProjeto conceitual de um sistema de bobinas RMP para o tokamak TCABREquilíbrio e estabilidade MHDFísica de Plasmas.MagnetohidrodinâmicaMagnetohydrodynamicsMHD equilibrium and stabilityPlasma Physics.TokamakTokamaksThe high confinement mode observed in tokamak plasmas is seen as the most promising operational regime for economically viable nuclear fusion power plants. A particular characteristic of the high confinement plasmas is the onset of periodic instabilities known as edge localized modes (ELMs). These instabilities generate unacceptably large heat fluxes on the divertor plates that erode the divertor and reduces significantly its life time on a future reactor. Therefore, there is a need to develop ELM control methods in large machines, such as ITER. Several experiments have demonstrated that the application of non-axisymetric resonant magnetic perturbations (RMPs), created by electric currents flowing in localised coils outside the plasma, can be used to control ELMs. Due to its efficiency, ELM control coils, also called RMP coils, were added to ITER baseline project. Although the RMP coils have been successfully used to suppress ELMs in various tokamaks, the numerical modelling of these plasma discharges reveal that current physical models are not capable of describing satisfactorily the observed effects. The lack of a trustworthy physical model to describe the impact of RMP fields in tokamak plasmas is a central topic when plasma physics scientists try to predict the plasma reaction to the RMP fields in ITER. In order to enhance the numerical results reliability, carefully designed experiments to validate physical models are being realised in several tokamaks around the globe. Here in Brazil, a significant upgrade of the TCABR tokamak, operated at Plasma Physics Laboratory of Institute of Physics of the University of São Paulo, is in progress. In this upgrade, it is planned the installation of six sets of RMP coils, which enable the TCABR to test physical models used to predict the plasma response to RMP fields. This work has the objective of designing the RMP coil sets that will be installed in TCABR, which enables the validation of physical models in a wide variety of plasma scenarios, RMP field configurations and magnetic spectra with a large range of poloidal and toroidal harmonics.O modo de alto confinamento observado em plasmas de tokamaks é visto como o regime operacional mais promissor para se obter usinas de energia a fusão nuclear economicamente viáveis. Uma característica particular desses plasmas de alto confinamento é a presença de instabilidades periódicas conhecidas como edge localized modes (ELMs). Estas instabilidades causam fluxos de calor inaceitavelmente altos nas placas do divertor de modo que a erosão causada por tal fluxo reduzirá significativamente o tempo de vida do divertor em um futuro reator. Há, portanto, a necessidade de desenvolver métodos de controle de ELMs em máquinas de grande porte, como o ITER. Tem sido amplamente demonstrado que a presença de perturbações magnéticas ressonantes (resonant magnetic perturbations - RMPs) não-axissimétricas, criadas por correntes elétricas fluindo em bobinas localizadas fora do plasma, podem ser usadas para suprimir ELMs. Devido à sua eficiência, bobinas de controle de ELMs, comumente chamadas de bobinas RMP, foram adicionadas ao projeto base do ITER. No entanto, embora tais bobinas têm sido usadas com sucesso para suprimir ELMs em vários tokamaks, a modelagem numérica dessas descargas revela que os modelos físicos atuais ainda não são capazes de reproduzir satisfatoriamente os efeitos observados. A falta de um modelo físico confiável que descreva o impacto de campos RMP em plasmas de tokamak é uma questão fundamental quando se tenta prever a resposta de plasmas criados no ITER à campos RMP. Para melhorar a confiabilidade dos resultados destes códigos, experimentos cuidadosamente projetados para validar modelos físicos estão sendo realizados em vários tokamaks ao redor do mundo. Aqui no Brasil, um upgrade significativo do tokamak TCABR, operado pelo Laboratório de Física de Plasmas do Instituto de Física da Universidade de São Paulo, está em andamento. Neste upgrade, está planejado a instalação de seis conjuntos de bobinas RMP que permita a criação de ambientes no TCABR em que os modelos físicos usados para prever a resposta de plasmas à campos RMP possam ser validados. Este trabalho tem como objetivo projetar o sistema de bobinas RMP que será instalado no tokamak TCABR. As bobinas RMP serão projetadas de modo a permitir a validação de modelos físicos em uma ampla variedade de cenários de plasma, de configurações geométricas de campo RMP e de espectro com amplo conteúdo de harmônicos toroidais e poloidais.Biblioteca Digitais de Teses e Dissertações da USPCanal, Gustavo PaganiniSalvador, Felipe Machado2022-10-07info:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/masterThesisapplication/pdfhttps://www.teses.usp.br/teses/disponiveis/43/43134/tde-21112022-130617/reponame:Biblioteca Digital de Teses e Dissertações da USPinstname:Universidade de São Paulo (USP)instacron:USPLiberar o conteúdo para acesso público.info:eu-repo/semantics/openAccesseng2023-02-14T15:01:58Zoai:teses.usp.br:tde-21112022-130617Biblioteca Digital de Teses e Dissertaçõeshttp://www.teses.usp.br/PUBhttp://www.teses.usp.br/cgi-bin/mtd2br.plvirginia@if.usp.br|| atendimento@aguia.usp.br||virginia@if.usp.bropendoar:27212023-02-14T15:01:58Biblioteca Digital de Teses e Dissertações da USP - Universidade de São Paulo (USP)false
dc.title.none.fl_str_mv Conceptual design of a system of RMP coils for the TCABR tokamak
Projeto conceitual de um sistema de bobinas RMP para o tokamak TCABR
title Conceptual design of a system of RMP coils for the TCABR tokamak
spellingShingle Conceptual design of a system of RMP coils for the TCABR tokamak
Salvador, Felipe Machado
Equilíbrio e estabilidade MHD
Física de Plasmas.
Magnetohidrodinâmica
Magnetohydrodynamics
MHD equilibrium and stability
Plasma Physics.
Tokamak
Tokamaks
title_short Conceptual design of a system of RMP coils for the TCABR tokamak
title_full Conceptual design of a system of RMP coils for the TCABR tokamak
title_fullStr Conceptual design of a system of RMP coils for the TCABR tokamak
title_full_unstemmed Conceptual design of a system of RMP coils for the TCABR tokamak
title_sort Conceptual design of a system of RMP coils for the TCABR tokamak
author Salvador, Felipe Machado
author_facet Salvador, Felipe Machado
author_role author
dc.contributor.none.fl_str_mv Canal, Gustavo Paganini
dc.contributor.author.fl_str_mv Salvador, Felipe Machado
dc.subject.por.fl_str_mv Equilíbrio e estabilidade MHD
Física de Plasmas.
Magnetohidrodinâmica
Magnetohydrodynamics
MHD equilibrium and stability
Plasma Physics.
Tokamak
Tokamaks
topic Equilíbrio e estabilidade MHD
Física de Plasmas.
Magnetohidrodinâmica
Magnetohydrodynamics
MHD equilibrium and stability
Plasma Physics.
Tokamak
Tokamaks
description The high confinement mode observed in tokamak plasmas is seen as the most promising operational regime for economically viable nuclear fusion power plants. A particular characteristic of the high confinement plasmas is the onset of periodic instabilities known as edge localized modes (ELMs). These instabilities generate unacceptably large heat fluxes on the divertor plates that erode the divertor and reduces significantly its life time on a future reactor. Therefore, there is a need to develop ELM control methods in large machines, such as ITER. Several experiments have demonstrated that the application of non-axisymetric resonant magnetic perturbations (RMPs), created by electric currents flowing in localised coils outside the plasma, can be used to control ELMs. Due to its efficiency, ELM control coils, also called RMP coils, were added to ITER baseline project. Although the RMP coils have been successfully used to suppress ELMs in various tokamaks, the numerical modelling of these plasma discharges reveal that current physical models are not capable of describing satisfactorily the observed effects. The lack of a trustworthy physical model to describe the impact of RMP fields in tokamak plasmas is a central topic when plasma physics scientists try to predict the plasma reaction to the RMP fields in ITER. In order to enhance the numerical results reliability, carefully designed experiments to validate physical models are being realised in several tokamaks around the globe. Here in Brazil, a significant upgrade of the TCABR tokamak, operated at Plasma Physics Laboratory of Institute of Physics of the University of São Paulo, is in progress. In this upgrade, it is planned the installation of six sets of RMP coils, which enable the TCABR to test physical models used to predict the plasma response to RMP fields. This work has the objective of designing the RMP coil sets that will be installed in TCABR, which enables the validation of physical models in a wide variety of plasma scenarios, RMP field configurations and magnetic spectra with a large range of poloidal and toroidal harmonics.
publishDate 2022
dc.date.none.fl_str_mv 2022-10-07
dc.type.status.fl_str_mv info:eu-repo/semantics/publishedVersion
dc.type.driver.fl_str_mv info:eu-repo/semantics/masterThesis
format masterThesis
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url https://www.teses.usp.br/teses/disponiveis/43/43134/tde-21112022-130617/
dc.language.iso.fl_str_mv eng
language eng
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dc.rights.driver.fl_str_mv Liberar o conteúdo para acesso público.
info:eu-repo/semantics/openAccess
rights_invalid_str_mv Liberar o conteúdo para acesso público.
eu_rights_str_mv openAccess
dc.format.none.fl_str_mv application/pdf
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dc.publisher.none.fl_str_mv Biblioteca Digitais de Teses e Dissertações da USP
publisher.none.fl_str_mv Biblioteca Digitais de Teses e Dissertações da USP
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reponame:Biblioteca Digital de Teses e Dissertações da USP
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reponame_str Biblioteca Digital de Teses e Dissertações da USP
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repository.name.fl_str_mv Biblioteca Digital de Teses e Dissertações da USP - Universidade de São Paulo (USP)
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