Study of impurity transport in negative and positive triangularity plasmas H/F

il y a 6 jours


SaintPaullèsDurance, Provence-Alpes-Côte d'Azur, France CEA Temps plein


Informations générales

Entité de rattachement

Le CEA est un acteur majeur de la recherche, au service des citoyens, de l'économie et de l'Etat.

Il apporte des solutions concrètes à leurs besoins dans quatre domaines principaux : transition énergétique, transition numérique, technologies pour la médecine du futur, défense et sécurité sur un socle de recherche fondamentale. Le CEA s'engage depuis plus de 75 ans au service de la souveraineté scientifique, technologique et industrielle de la France et de l'Europe pour un présent et un avenir mieux maîtrisés et plus sûrs.

Implanté au cœur des territoires équipés de très grandes infrastructures de recherche, le CEA dispose d'un large éventail de partenaires académiques et industriels en France, en Europe et à l'international.

Les collaboratrices et collaborateurs du CEA partagent trois valeurs fondamentales :

• La conscience des responsabilités

• La coopération

• La curiosité

Référence

Description de l'unité

"L'Institut de Recherche sur la Fusion par Confinement Magnétique est l'un des départements de la Direction de la Recherche Fondamentale du CEA. Depuis plus de 50 ans, son rôle est de mener des recherches sur une nouvelle source d'énergie : la fusion par confinement magnétique, en s'associant avec le programme Fusion européen. L'IRFM est installé sur le Centre CEA de Cadarache. Les activités de L'IRFM sont structurées autour de trois axes de recherches de développement :
- contribuer à la réalisation du projet ITER et ceux de l'Approche Elargie (tokamak JT-60SA principalement),
- préparer l'opération scientifique d'ITER, à travers des activités d'expérimentation et de contrôle, ainsi que de théorie et de modélisation,
- établir les bases du futur réacteur de fusion.
Ces activités sont intimement connectées à un effort tout particulier de formation des générations futures de physiciens et de technologues de la fusion. L'IRFM a à sa disposition de nombreuses plateformes de R&D et de tests, dont le tokamak WEST (pour Tungsten (w) Environnement Steady-State Tokamak), transformation de Tore Supra en banc de test pour ITER, le nouveau tokamak du CEA va permettre de tester l'un des composants clé d'ITER et de poursuivre les recherches en physique des plasmas, dans un contexte international grâce aux nombreuses collaborations mises en place."


Domaine

Physique du noyau, atome, molécule


Contrat

Stage


Intitulé de l'offre

Study of impurity transport in negative and positive triangularity plasmas H/F


Sujet de stage

A plasma scenario for a future fusion reactor must demonstrate low core impurity contamination. To this end, this internship aims to develop an algorithm that determines the transport coefficients of metallic impurities by analyzing experimental measurements and solving the impurity transport equation.


Durée du contrat (en mois)

6


Description de l'offre

Nuclear fusion in a tokamak is a promising source of energy. However, a question arises: which plasma configuration is most likely to produce net energy? To contribute to answering this question, during this internship (and possible subsequent PhD), we will study the impact of magnetic geometry, comparison between positive and negative triangularity, on the collisional and turbulent transport of tungsten (W). The performance of a tokamak strongly depends on the energy confinement it can achieve. The latter degrades significantly due to turbulent transport and radiation, primarily from W. On ITER, the tolerated amount of W in the core of the plasma is just 0.3 micrograms in 800 cubic meters of plasma volume. Experiments have shown that the negative triangularity (NT) plasma geometry is beneficial for confinement as it significantly reduces turbulent transport. With this geometry, it is possible to reach confinement levels similar to those of the ITER high confinement configuration (H-mode in positive triangularity), without the need for a minimum power threshold and without the associated plasma edge relaxations. However, questions remain: what level of W transport is found in NT compared to a positive geometry? What level of radiation can be predicted in future NT reactors? To address these questions, the objective of this internship is to develop an algorithm that determines the impurity transport coefficients from experimental measurements and by solving the impurity transport equation.

The internship duration is 6 months.


Moyens / Méthodes / Logiciels

Algorithm development based on open-source impurity transport and radiation code AURORA.


Profil du candidat

Physics or engineering backgroud


Site

Cadarache


Localisation du poste

France, Provence-Côte d'Azur, Bouches du Rhône (13)


Ville


Saint paul lez Durance

Critères candidat
Langues

Anglais (Courant)


Possibilité de poursuite en thèse

Oui


Disponibilité du poste

16/03/2026



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